ML20211E995

Proposed Tech Specs Correcting Inconsistencies Noted by in- House Review & Insp Rept 50-312/85-11

ML20211E995
Person / Time
Site:	Rancho Seco
Issue date:	06/13/1986
From:	SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
Shared Package
ML20211E983	List: ML20211E978 ML20211E995
References
NUDOCS 8606170089
Download: ML20211E995 (5)

Text

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RANCHO SEC0 UNIT 1

. TECHNICAL SPECIFICATIONS LIST OF TABLES Table Page 2.3-1 REACTOR PROTECTION SYSTEM TRIP SETTING LIMITS 2-9 3.5.1-1 INSTRUMENTS OPERATING CONDITIONS 3-27 3.6-1 SAFETY FEATURES CCNTAINMENT ISOLATION VALVES 3-40 149> 3.7-1 VOLTAGE PROTECTION SYSTEM RELAY TRIP VALUES 3-41a

< 3.7-2 VOLTAGE PROTECTION SYSTEM LIMITING CONDITIONS 3-41b 3.14-1 FIRE DETECTION INSTRUMENTS FOR SAFETY SYSTEMS 3-55 3.14-2 INSIDE BUILDING FIRE H0SE STATIONS 3-57a 3.15-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3-61 3.16-1 RADI0 ACTIVE GASES ~ EFFLUENT MONITORING INSTRUMENTATION 3-64 3.22-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3-83 3.22-2 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS 3 IN ENVIRO 14 MENTAL SAMPLES 4.1-1 INSTRUMENT SURVEILLANCE REQUIREMENTS 4-3 4.1-2 MINIMUM EQUIPMENT TEST FREQUENCY 4-8 4.1-3 MINIMUM SAMPLING FREQUENCY 4-9 4.2-1 CAPSULE ASSEMBLY WITHDRAWAL SCHEDULE AT DAVIS-BESSE 1 4-12b 149><

4.14-1 DESIGNATED SAFETY RELATED HYDRAULIC SNUBBERS 4-47d,e FUNCTIONALLY TESTED ONLY AS REQUIRED BY THE SNUBBER SEAL REPLACDiENT PROGRAM 4.17-1 ' MINIMUM NUMBER OF STEAM GENERATORS TO BE 4-56 INSPECTED DURING INSERVICE INSPECTION 4.17-2A STEAM GENERATOR TUBE INSPECTION 4-57 4.17-2B STEAM GENERATOR TUBE INSPECTION (SPECIFIC LIMITED AREA) 4-57a 4.19-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 4-64 SURVEILLANCE REQUIREMENTS 4.20-1 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 4-66 SURVEILLANCE REQUIREMENTS Proposed Amendment No.149 IX lIO 00$ bI0 P

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. RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Definitions

1. DEFINITIONS' The following terms are defined for uniform interpretation of these specifications.

1.1 RATED POWER Rated poweris a steady reactor core output of 2772 MWt.

1.2 REACTOR OPERATING CONDITIONS 1.2.1 Cold Shutdown The reactor is in the cold shutdown condition when it it subcritical by at least 1 percent ak/k and Tavg is no more than 200 F. Pressure is defined by Specification 3.2.1.

1.2.2 Hot Shutdown The reactor is in the hot shutdown condition when it is subcritical by at least 1 percent ak/k and Tavg is at or greater than 525 F.

1.2.3 Reactor Critical The reactor is critical when the neutron chain reaction is self-sustainig and Keff = 1.0.

1.2.4 Hot Standby The reactor is in the hot standhy condition when all of the following conditions exist:

A. Tavg is greater than 525 F.

B. The reactor is critical.

C. Indicated neutron power on the power range channels is less than 2 percent of rated power.

1.2.5 Power Operation The reactor is in a power operation condition when the indicated neutron power is above 2 percent of rated power as indicated on the power range channels.

1.2.6 ' Refueling Shutdown 149>< The reactor is in the refueling shutdown condition when the reactor is subcritical with a kegf no greater than 0.95 and the coolant tenperature at the decay heat remova pump suction is no more than Proposed Amendment 149 1-1 L-

• ' - . RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS

. Limiting Conditions for Operation

. 3.8 FUEL LOADING AND REFUELING Applicability Applies to fuel loading and refueling operations.

Objective l'

To ensure that-fuel loading and refueling operations are perfonaed in a responsible manner.

Specification i.

i 3.8.1 Radiation levels in the Reactor Building refueling area shall be monitored by R15026 and R15027.. Radiation. levels in the spent fuel

! storage-area shall be monitored by R15028. If any of these instruments i become inoperable, portable survey instrumentation, having the appropriate ranges and sensitivity to fully protect individuals involved in refueling operations, shall be used until the permanent instrumentation is returned to service.

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- 3.8.2 Core subcritical neutron flux shall be continously monitored by at least two neutron flux monitors, each with continous indication available, i.

whenever core geometry is being changed. When core geometry is not being changed, at least one neutron flux monitor shall be in service.

l 3.8.3 At least one decay heat removal pump and cooler shall be operable.

3.8.4 During reactor vessel head removal and while loading and unloading fuel from the reactor, the boron concentration shall be maintained at not

'149> - less than 1800' ppm, or at a concentration sufficient to ensure a keff 4 no greater than 0.95, whichever is the more restrictive.

3.8.5 Direct communications between the control room and the refueling personnel in the Reactor Building shall exist whenever changes in core geometry a:e taking place.

3.8.6 During' the handling of irradiated fuel in-the Reactor Building at least i~ one door on the personnel and emergency hatches shall be closed. The

equipment hatch cover shall-be in place with a minimum of four bolts

-securing the cover to the sealing surfaces.

3.8.7 Isolation valves in lines containing automatic containment isolation valves shall be operable, or at least one shall be in a safety features position.

3.8.8 When two irradiated fuel assemblies are being handled simultaneously within the fuel transfer canal, a minimum of 10 feet separation shall be maintained between the assemulies at all times. Irradiated fuel assemblies may be handled with the auxiliary bridge crane provided no other irradiated fuel assembly is' being handled in the fuel transfer canal.

Proposed Amendment 149 3-44

. RANCHO SECO UNIT 1 TECHNICAL' SPECIFICATIONS Limiting Conditions for Operation 3.8.9 If any of the above specified. limiting conditions for fuel loading and refueling are not met, movement of fuel into the reactor core shall cease; action shall be initiated to correct the conditions so that the specified limits are met, and no operations which may increase the reactivity of the core shall be made.

3.8.10 The Reactor Building purge system, including the radiation monitors, R15001A and R15001B, shall be tested and verified to be operable immediately prior to refueling operations.

3.8.11 Irradiated fuel shall not be removed from the reactor until the unit 4 has been subcritical for at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

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3.8.12 'No loads will be handled over irradiated fuel stored in the spent fuel pool, except the fuel assemblies themselves. A dead weight load test .

at the rated load will be performed on the Fuel Storage Building handling bridge prior to each refueling. ,

Bases Detailed written procedures will be available for use by refueling personnel.

These procedures, the above specifications, and the design of the fuel handling equipment, as described in subsection 9.7 of the FSAR incorporating built-in interlocks and safety features, provide assurance that no incident could occur during the refueling operations that would result in a hazard to

, public health and safety. If no change is being made in core geometry, one flux monitor is sufficient. This permits maintenance on the instrumentation.

Continuous monitoring of radiation levels and neutron flux prevides immediate indication of an unsafe condition. The decay heat removal pump i: used to maintain a uniform boron concentration.1 The refueling boron concentration indicated in Specification 3.8.4 will be maintained to ensure that the more restrictive of the following reactivity conditions is met:

149H 1. Either. a keff of 0.95 or less, or

2. A boron concentration of >1800 ppm.

Specification 3.8.5 allows the control room operator to infom the Reactor Building personnel'of any impending unsafe condition detected from the main l control board indicators during fuel movement.

The specification requiring testing Reactor Building purge termination is to verify that these components will function as required should a fuel handling accident occur that resulted in the release of significant fission products.

!- Specification 3.8.11 is required as the safety analysis for the fucl handling accident was based on the assumption that the reactor had been shJtdown for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and all 208 fuel pins in the hottest fuel assembly fail, releasing all E

gap activity.2 4 Proposed Amend:nent 149 3-45

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RANCHO SECO UNIT 1 f

. TECHNICAL SPCCIFICATIONS l Survaillance Standards

.. TABLE 4.1-3 MIMIMUM SAMPLING FREQUENCY

. Item Check ..

Frequency-  !

1. Reactor coolant a. Radio-chemical pgglysistil M 149>< E deteminationt9' Semiannually

b. Gross activityti) (3) 3/ week

c. Tritium radioactivity M ,

d. Chemistry (C1 and 02 ) 3/ week

e. Boron concentration .2/ week

f. Fluoride M

i - 2. Borated water storage Boron concentration M and after each tank water sample makeup

3. Core flooding tank Boron concentration (3) M and after each water sample makeup l 4. Spent fuel storage Boron concentration M and after each water sample makeup

5. Secondary coolant a. Gross activityI3) Weekly

b. Iodine analysis (2)(3) Weekly 149>< 6. Concentrated boric Boron concentration (5) 2/ week and after acid tank each makeup I 1497 4 4 7. Spray additive tank Na0H concentration (3) Q and after each makeup s 149>

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< 8. Blowdown from cooling Gross activity (3) M

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.(1)When radioactivity level is greater than 20 percent of the limits of

Technical Specification 3.1.4, the sampling. frequency shall be increased to a minimum of once each day.

(2)When gross . activity increases by a factor of two above normal, an iodine analysis will be made and perfomed thereafter when the gross activity increases by ten percent.

(3)Not perfomed during cold shutdown.

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< (4)5 determination will be started when gross beta-gamma activity analysis indicates greater than 10pCi/ml and'will be redetermined each 10gCf /ml

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increase in gross beta-gamma activity analysis. A radio chemical analysis for this purpose shall consist of a quantitative measurement of 95% of -

radionuclides in reactor coolant with half lives of >30 minutes.

149>< (5)Not performed during cold shutdown except during refueling operations.

Proposed Amendment 149 4-9