K-REACTOR TECHNICAL SPECIFICATIONS

The latest safety documentation update for K-Reactor in Cold Standby is discussed in Section 4.0 of this BIO and-consists primarily of the K-Reactor Safety Analysis Report ef 3-5), the K-Reactor Technical Specifications (Ref. 3-6), and the K-Reactor Cold Standby Plan O f. 3-3). These documents provide for storage and handling of unirradiated fuel and irradiated components and storage and processing of contaminated moderator. The latest safety documentation for L-and F-Reactor Disassembly Basins is also discussed in Section 4.0 of this BIO. These documents consist mainly of the L- and P-Reactor T hnical Specifications, L-Reactor Cold Shutdown Plan, P-Area Standby Plan, and the Transfer Packages for 100-L and P Area Facilities. These documents provide for storage and handling of irradiated components. 

El 1991, the Plant Operating Specifications (POS) C ef 4-22) for K-Reactor were originally issued to spedty the balance of the safety envelope requirements not covered by the K-Reactor Technical Specifications. However, the items for this expanded safety envdope were judged to warrant dmiiar rigor and controls as the Techmcal Spedfications. The POS inocedure is to be used in coiyunction with the Tedimcal Spedfications. Ei 1994, the POS has been updated to reflect K-Reactor in Cold Standby (Ref 4-22). 

As discussed in Section 4.0 of this BIO, the documents that serve as the existing authorization basis for K-Reactor during Cold Standby and this BIO constitute the authorization basis for K-Reactor in Cold Standby. The BIO for K-Reactor in Cold Standby brings the authorization basis documents together by reference in one document. Additionally, the BIO provides supplementary information in areas such as DOE Order compliance, safety analyses, and additional administrative controls. This document, and the other BIOs discussed above, will be used to satisfy the K-Reactor Technical Specification requirement to update the SAR annually. After DOE proval of these BIOs (and any additional BIOs to cover additional missions), the authorization basis will consist of the present SAR and BIOs. 

WSRC Savannah River K-Reactor Technical Specifications, Rev. 0,... 

Letter, S. Richardson to P.D. Rice, "K-Reactor Technical Specifications WSRC-TS-10003 Revision 1," March 15, 1991. 

Savannah River Site Production Reactor Technical Specifications. K Production Reactor. WSRC-TS-10003, Rev. 16, Westinghouse Savannah River Company, Aiken, SC, November 1,1993. 

In order to prevent a credible criticality event involving the handling of fuel assen lies in the K-, L-, and P-Reactor Disassembly Basins during normal operations, the Technical Specifications (Ref. 6-3, 6, 6-5), Limiting Conditions for Operations 3.9.3, impose restrictions for handling and storing fiiel.as5 nblies in the Disassembly Basins. 

Methodically Engineered Restructured and Improved Technical Specifications [MERITS]). The current L, andJ >Reactor Technical Spcdficatioas meet the intent of DOE Order 5480.22 ef. 7-20), but da not comply with some of the content and format provisions. WSRC has submitted a Compliance Assessment and Implementation Rqjoit (Ref. 7-21) for DOE Order 5480.22 with a compliance schedule and compensatory measures for K-Reactor and an exemption request for L- and P-Reaaors. 

K , the infinite multiplication foctor, for a stored. array, of assemblies containing fresh 3.5 wl% fuel y ould be 0.90. This criterion was adhered to to meet foe, current technical specification limit for foe 1P2 reactor.,, ... 

SRSPO and SRRO reviewed the upgraded K-Reactor SAR to determine if it complied with the approved upgrade plan. The chapters, which were rewritten in mid-1990, generally conformed with the plan however, a number of additional new DOE comments were generated. For example, the SER requires a list of safety-related systems and components in the SAR, but the list has not yet been included or referenced. Other comments relate to the accuracy and usefulness of the SAR for making safety evaluations, establishing the Technical Specifications, and identifying the most currently applicable safety analysis bases or sources. 

The Phase 1 and Phase 2 Technical Specifications were submitted to DOE for approval as WSRC-TS-10003 Revision 0 on December 18, 1990 (Reference 5). At DOE request, WSRC included a new Technical Specification for the Ultimate Heat Sink. In the submittal, WSRC noted that the review verified the Limiting Conditions for Operation, and the associated Surveillance Requirements applicable to chargeback and shutdown. DOE approved Revision 0 on January 25, 1991,(Reference 6). Until WSRC-TS-10003, Rev. 0, is fully implemented, WSRC will comply with the existing OPST-TS-105 after implementation of WSRC-TS-10003, DPST-TS-105 will be withdrawn for the K-Reactor. Additionally, there are a number of open items remaining that relate to startup and operations, including ... 

RTAP has prepared decision-point review documents for the Safety Function Status Trees that document the basis for technical data and numerical values used in the EOPs. The documents have been reviewed and approved by Reactor Safety Research, Reactor Operations Department, and Reactor Technology Department. The documents are not identified by a specific document number, but are part of the procedure package for DPS0L-105-MC-29-K, Rev. 2, "Vital Safety Function Monitoring-Emergency Condition" (Reference 3), presented for review and approval by the Operations and Maintenance Review and Approval Committee (OMPRAC). The documents become part of the procedure history file and are formally documented. Changes to the documents will not be tracked and reviewed since the documents are for historical purposes only. Administrative controls are required to ensure that all values in the EOPs are adequately maintained and revised as necessary. The staff determined that the EOP-decision point review documents provide the basis for the EOPs, but lack the... 

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