ML20205T279

Amend 84 to License DPR-54,establishing Limiting Conditions for Operation Based on Spent Fuel Pool (SFP) Water Temp Including Requirements for Use of DHR Sys as Alternate/ Supplemental SFP Cooling Means When SFP Limits Reached

ML20205T279
Person / Time
Site:	Rancho Seco
Issue date:	03/31/1987
From:	Stolz J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20205T264	List: ML20205T260 ML20205T279 ML20205T302
References
TAC-56689, NUDOCS 8704070257
Download: ML20205T279 (5)

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UNITED STATES NUCLEAR REGULATORY COMMISSION n a wAsMNGTON, D. C. 20066 4, .....s/

SACRAMENTO MUNICIPAL UTILITY DISTRICT DOCKET NO. 50-312 RANCHO SEC0 NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 84 License No. DPR-54

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Sacramento Municipal . Utility District (the licensee) dated December 13, 1984, as revised April 26, 1985, supplemented May 22, 1985, and superseded October 30, 1985, complies with the standards and requirements of the Atomic Eneroy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I;

8. The facility will operate in conformity with the application, the the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51

! of the Commission's regulations and all applicable requirements have been satisfied.

l 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment,

( and paragraph 2.C.(2) of Facility Operating License No. DPR-54 is hereby j amended to read as follows:

l 8704070257 870331 PDR ADOCK 05000312 p PDR

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Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 84, are hereby incorporated in the license. The licensee shall operate-the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuance.

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FOR THE NUCLEAR REGUI.ATORY COMMISSION b

oh F. Stolz, Direc PWR Proiect Director We #6 Division of PWR Licensina-R

Attachment:

Changes to the Technical Specifications Date of Issuance: March 31,1987 9

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ATTACHMENT TO LICENSE AMENDMENT NO. 84-FACILITY OPERATING LICENSE NO. DPR-54 DOCKET NO. 50-312 Replace the following pages of the Appendix "A" Technical Specifications with the attached _pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

Remove Insert fii iii 3-46a Y

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, RANCHO SECO UNIi 1 TECHNICAL SPECIFICATIONS TABLE OF CONTENTS (Continued)

Sec tion Page 3.1.6 Leakage .- 3-12 3.1.7 Moderator Temperature Coefficient of Reactivity 3-15 3.1.8 Low Power Physics Testing Restrictions 3-15 3.1.9 Control Rod Operation 3-16 3.2 HIGH PRESSURE INJEGTION, CHEMICAL ADDITION, AND LOW 3-17 TEMPERATURE OVERPRESSURE PROTECTION (LTOP) SYSTEMS 3,3- EMERGENCY CORE COOLING, REACTOR BUILDING EMERGENCY C00 LING, 3 19 AND REACTOR BUILDING SPRAY SYSTEMS 3.4 STEM AND POWER CONVERSION SYSTEM 3-23 3.5 INSTRUMENTATION SYSTEMS 3-25 3.5.1 Operational Safety Instrumentation 3-25 3.5.2 Control Rod Group and Power Distribution Limits 3-31 3.5.3 Safety Features Actuation System Setpoints 3-34 3.5.4 incore Instrumentation 3-36 3.5.5 Accident Monitoring Instrumentation 3-38a 3.6 REACTOR BUILDING 3-39 3.7 AUXILIARY ELECTRICAL SYSTEMS 3-41 l 3.8 FUEL LOADING AND REFUELING 3-44 3.9 SPENT FUEL P0OL 3-46a l

. 3.10 SECONDARY SYSTEM ACTIVITY 3-47 3.11 REACTOR BUILDING POLAR CRANE AND AUXILIARY HOIST 3-49 3.12 SHOCK SUPPRESSORS (SNUBBERS) 3-51 3.13 AIR FILTER SYSTEMS 3-52 t, 3.14 FIRE SUPPRESSION 3-53 3.14.1 Instrumentation 3-53 3.14.2 Water System 3-53 3.14.3 Spray and Sprinkler Systems 3-56 3.14.4 CO System 3-56 2 ,

I Amendment No. 75, Ap,g'gr % 84 e III

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS-Limiting Conditions for Operation 3.9 SPENT FUEL POOL Applicability e's Applies to the Spent Fuel Pool Cooling System.

Objective ,

To provide for adequate cooling of the Spent Fuel Pool to ensure that the pool temperature is kept low enough to prevent boiling.

Specification

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3.9.1 One train of the Decay Heat Removal System (DHRS) must be put in service to provide alternate cooling for the Spent Fuel Pool if the bulk coolant temperature reaches 140 0F and the Spent Fuel Pool Cooling System is inoperable, and as a supplement to the nSpent Fuel Pool Cooling System if a maximum temperature of 180 F is exceeded.

3.9.2 If a train of the DHRS is being used to provide alternate cooling for the Spent Fuel Pool, it shall be declared inoperable for other purposes and the provisions of Technical Specification 3.3.2 shall apply unless the reactor is in Cold Shutdown.

3.9.3 Use of the OHRS for Spent Fuel Pool cooling shall be limited to no more than 100 cumulative hours (when not in Cold Shutdown) in any 12-month period.

3.9.4 Reactor shutdown must be initiated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> if the Spent Fuel Pool bulk coolant temperature reaches 180 F, and the reactor must be in Cold Shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

BASES This specification provides a method to ensure that the Spent Fuel Pool bulk temperature does not reach the boiling point. The use of a train of the

. Decay' Heat Removal System (OHRS), per Operating Procedure A.21, Section 7.3, provides immediate alternate cooling capability to ensure this. Either train of the DHRS can easily be lined up for Spent Fuel Pool cooling by opening two manual valves (DHS-032 and DHS-055 or -56), one motor operated ,

valve (HV-26047 or 46), and starting the appropriate decay heat pump (P-261A or 8). However, since use of the DHRS train for Spent Fuel Pool cooling effectively removes it from its normal service, an operating duration limit of 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> per 12-month period is imposed.

References

[1] Licensing Report for High Density Spent Fuel Storage Racks for Rancho Seco.

[2] Time to Boil Calculation, Supplement No. 2 to Themo-Hydraulic Calculations for Rancho Seco Nuclear Station; Report No. TM-661.

Amendment ?[o.84 3-46a

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