ML20210N892

Proposed Changes to Tech Spec 1.2.6 & 3.8.4 Re Boron Concentration & Shutdown Margin,Respectively,In Response to Inconsistencies Noted in Insp Rept 50-312/85-11

ML20210N892
Person / Time
Site:	Rancho Seco
Issue date:	04/30/1986
From:	SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
Shared Package
ML20210N890	List: ML20210N884 ML20210N892
References
NUDOCS 8605050311
Download: ML20210N892 (6)

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.ag ATTACHMENT III DESCRIPTION OF PROPOSED CHANGES

1. List of Tables, Pase ix: Added Tables 3.7-1 and 3.7-2, and deleted Tables 4.10-1 and 4.10-2.

2. Specification 1.2.6, Page 1-1: Deleted reference to 1% a k/k with all rods removed, and added the requirement of keff no greater than 0.95.

3. Specification 3.8.4, Page 3-44: Changed boron concentration from 1850 ppm to 1600 ppm and added keff no greater than 0.95 whichever is more restrictive.

4. Bases for Specification 3.8, Page 3-45: Deleted reference to "all rods removed."

8605050311 860430 PDR ADOCK 05000312 P PDR

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RANCHO SECO 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 CONTAINMENT ISOLATION VALVES 3-40 126> 3.7-1 VOLTAGE PROTECTION SYSTEM RELAY TRIP VALUES 3-41a 4 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 3-86 IN ENVIRONMENTAL 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 126><

4.14-1 DESIGNATED SAFETY RELATED HYDRAULIC SNUBBERS 4-47d,e FUNCTIONALLY TESTED OHLY AS REQUIRED BY THE SNUBBER SEAL REPLACEMENT 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 SURVEILLANCF REQUIREMENTS l

4.20-1 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION 4-66 SURVEILLANCE REQUIREMENTS Proposed Amendment No. 126, Rev. 1 ix l l

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Definitions

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

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

1.2 k,.CTOR OPERATING CONDITIONS 1.2.1 Cold Shutdown The reactor is in the cold shutdown condition when it is 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 standby condition when all of the following ccnditions 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 126x The reactor is in the refueling shutdown condition when the reactor is subcritical with a keff no greater than 0.95 and the coolant temperature at the decay heat remova pump suction is no more than Proposed Amendment 126, Rev.1 1-1

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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 To ensare that fuel loading and refueling operations are performed in a responsible manner.

l Specification 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 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.

3.8.2 Core subcritical neutron flux shall be continously ranitored by at least two neutron flux monitors, each with continous indication an !!able, whenever core geometry is being changed. When core geome Py is not being changed, at least one neutron flux monitor shall se in service.

3.8.3 At least one decay heat removal pump and cooler shall be operAle-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 126> less than 1800 ppm, or at a concentration sufficient to ensure a kerf

< 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 are taking place.

3.8.6 During the handling of irradiated fuel in the Reactor Building at least 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 10 lines containing automatic containment isolation valves shall be operable, or at least one shall be in a safety features I 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 assem511es 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 126, Rev. 1 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 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 />.

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 atove 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, provise 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 fl Jx provides imediate indication of an unsafe condition. The decay heat removal pump is used to maintain a uniform boron concentration.l 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:

126x 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 inform 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 fuel handling J accident was based on the assumption that the reactor had been shutdown for 72 )

hours and all 208 fuel pins in the hottest fuel assembly fail, releasing all gap activity.2 l

Proposed Amendment 126, Rev. 1 1 3-45 l

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards i TABLE 4.1-3

, MIMIMUN SAMPLING FREQUENCY

. Item Check ,,, Frequency

1. Reactor coolant a. Radfo-chemical gnalysisul M 126>< E determination (4) Semiannually

b. Gross activityll) (3) 3/ week

c. Tritium radioactivity M j d. Chemistry (C1 and 02 ) 3/ week

e. Boron concentration 2/ week l f. Fluoride M

2. Borated water storage Boron concentration M and af ter each tank water sample makeup i

3. Core flooding tank Boron concentration (3) M and af ter each water sample makeup I

4. Spent fuel storage Baron concentration M and af ter each water sample makeup f

5. Secondary coolant I3) Weekly I

a. Gross analysis

b. Iodine activity (2)(3) Weekly 126>< 6. Concentrated boric Boron concentration (5) 2/ week and after ,

acid tank each makeup i i

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< 7. Spray additive tank NaOH concentration (3) Q and after each makeup 126>

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

(1)When radioactivity level is groter than 20 percent of the limits of i Technical Specification 3.1.4, the sampling frequency shall be increased to a

minimum of once each day, i (2)When gross activity increases by a factor of two above normal, an iodine l analysis will be made and performed thereaf ter when the gross activity increases by ten percent.

(3)Not performed during cold shutdown.

126>

4 I4)E determination will be started when gross beta-gamma activity analysis indicates greater than 10pC1/ml and will be redetermined each 10pCi/ml 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.

126>< (5)Not performed during cold shutdown except during refueling operations, i Proposed Amendment 126, Rev.1 4-9 i

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