ML20134A205

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Proposed Tech Spec Section 3.9 Re Adequate Cooling of Spent Fuel Pool to Ensure Pool Temp Low Enough to Prevent Boiling & Incorporating NRC Recommended Duration Limit on Use of DHR Sys as Alternate Means of Cooling
ML20134A205
Person / Time
Site: Rancho Seco
Issue date: 10/30/1985
From:
SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
Shared Package
ML20134A199 List:
References
TAC-56689, NUDOCS 8511040267
Download: ML20134A205 (2)


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-RANCHO SECO UNIT 1

j gr TECHNICAL SPECIFICATIONS iy ~. '

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TABLE OF CONTENTS (Continued)-

--Section -

Page 3-12' I

-3.1.6-Leakage 3.1.7 Moderator Temperature Coefficient of Reactivity 3-15 3.1.8 Low Power Physics Testing Restrictions 3-15b b-3.1.9

_ Control Rod OperatiEn -

3-16 3.2 HIGH PRESSURE INJECTION AND THE CHEMICAL ADDITION SYSTEMS 3-17 3.3 EMERGENCY CORE COOLING, REACTOR BUILDING EMERGENCY COOLING, AND REACTOR BUILDING SPRAY SYSTEMS 3,-19 c

3.4 STEAM AND POWER CONVERSION SYSTEM 3-23 f

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' 3.6 REACTOR BUILDING 3-39 3.7 AUXILIARY ELECTRICAL SYSTEMS 3-41 3.8 FUEL LOADING-AND REFUELING 3-44 112>< 3.9.

SPENT FUEL POOL 3-46a 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 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-

'C02 System 3-56 Proposed Amendment No. 112, Rev. 2 fii

-8511040267 a51030g2 DR ADOCK O

RANCHO SECO tJNIT 1 TECHNICAL SPECIFILATIONS

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Limiting Conditions for Operation 3.9 SPENT FUEL' POOL Applicability Applies to the Spent Fuel Pool Cooling System.

Objective To provide for adequate cooling of the Spen'. Fuel Pool to ensure that the pool temperature is kept low enough to p event boiling.

Specification

3.9.1 One train of the Decay Heat Removal Syste., (DHRS) must be put in service to provide alternate cooling for the Snsnt Fuel Pool if the coolant temperature reaches 140 and the Spent Fuel Pool Cooling System is inoperable, and as a supplement to the Spent 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 considered as if it is inoperable and the provisions of Technical Specification 3.3.2

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shall apply unless the reactor is in Cold Shutdown.

I 3.9.3 Use of the DHRS for Spent Fuel Pool cooling shall be' limited to no more than 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> when not in cold shutdown in any 12-month k

period.

3.9.4 Reactor shutdown must be initiated immediately if the Spent Fuel Poo'. bulk 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 teer.perature does not reach the boiling point. The use of a train of the i.

Decay Heat Removal System (DHRS), 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 B).-

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.

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References

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

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

Proposed Amandment No. 112, Revision 2 3-46a 1

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