ML19337A647

Tech Spec Changes for Sections 1.0,3.5,4.5 & 6.3 & Addl Sections 3.13 & 4.13 to App a of License DPR-16.Clarifying Shift Technical Advisor Program

ML19337A647
Person / Time
Site:	Oyster Creek
Issue date:	09/23/1980
From:	JERSEY CENTRAL POWER & LIGHT CO.
To:
Shared Package
ML19337A642	List: ML19337A641 ML19337A647
References
NUDOCS 8009290369
Download: ML19337A647 (13)

Text

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V JERSEY CENTRAL POWER 6 LIGHT COMPANY OYSTER CREEK NUCLEAR GENERATING STATION (DOCKET No. 5U-219 )

s PROVisl0NAL OPERATING LICENSE No. JPR-16 Applicant hereby requests the Commission to change Appencix A to the above captioned license as follows:

1. Sections to be changed:

Sections 1.0, 3.5, 4.5 and 6.3.

Sections to be edded 3.13 and 4.13

2. Extent of Changes:

Modify Technical Specification to encompass NUREG 0578 Category "A"

3. Changes recuestec:

As per the attached Technical Specification pages 1.0-1, 3.5-la, 3.5-1b, 3.5-13a, 3.13-1, 3.13-2, 3.13-3, 4.5-4, 4.13-1, 4.13-2 , 6-2c anc 6-2c.

4 Discussion:

The subject changes are a result of NUREG 0578 Category "A" items and address the areas of automatic containment isolation valves, accident monitoring instrumentation and the shif t technical advisor.

Sections 3.5 and 4.5 have been modified to include a list of containment isolation valves that are actuated by diverse containment isolation signals.

Section 6.5 has been modified to include the qualifications of the shift technical advisor. Sections 3.13 and 4.13 have been added to accommodate the requirements for accident monitoring instrumentation.

8009200309

1.0-1 1.b PL ACE l'1 SHUTD0'/l CONDl T I 0'i Proceed with and maintain an uninterrupted normal plant shutcown operation until inc shutccan Condition is net.

1.9 PL ACE I!! COLD 5+idTD0!.N CorID I TION Proceed w i th and maintain an uninterrupted normal plant shutcown operation until the colc shutdown Condition is met.

1.10 PL ACE IN ISOLATED C0!!DI TIO!l Proceed w i th and maintain an uninterruoted normal isolation of the reactor f r xi the turbine conuenser system including closure of the main steam isolation v a l v es .

1.11 REFUEL !.'005 Ine r e ac t or is in the ref uel mode when the reactor mode sw i tch is in the refuel moco position and there is fuel in the reactor vessel. In this modo the refuel!ng platforn interlocks are in operation.

1.12 REFUELING OUTAGE For the purpose of designating frequency of testing and surveillance, a ref uel ing outage shal l mean a regular ly scheduled ref uel ing outage; however, wnere such outages occur w i th in 8 months of the end of the prev ious ref uel ing outage, the test or surveiiIance need not be per f ormed untii the next regul ar 1y scheduled outage. Following the first rotueling Outage, the time between successive tests or surveil lance shal l not exceed 20 months.

1.13 PRit/A9Y CONTAIN!ENT INTEGRITY P r imur / containment integrity means tnat the drywell and adsorption chamber are closed and all of tne following concitions are satisfied:

A. All non-a u tom at ic pr imar y containment isolation v alves which are not recuired to be open for plant operation are closed.

6. At least one door in the air lock is closed and sealed.

C. All automatic containment isolation valves speci f iec in Table 3.3.2 are operable or are securca in the closed position.

O. All blind flanges and manways are closed 1.1a SECONDARY CONTAIN Tli INTEGRITY S econd ar y containment integr ity means that the reactor building is closed and the following conditions are met:

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3.5-la

c. The reactor coolant system is -taintained at Iess than 212 F and vented.

d. At least one core spray pump, and system componen ts necessar y to deliver rated core spray flow to the reactor vessel, must remain operable to the extent that tne pump and any necessary valves can be started or operated from the control room or from local control stations, and the torus is mechanically intact.

e. (1 ) No work shall be performed on the reactor or its connected systems which could result in lowering the reactor water level to less than 4 '8" above the top of the active f uel and the condensate storage tank level is greater than th irty (30 ) feet (300,000 gallons). At least two redundant systems incl ud ing core spray pumps and system components must remain operable as defined in d. above.

or (2) The reactor vessel head, fuel pool gate, and separator-dryer pool gates are removed and the water level is above elevation 117 feet.

NOTE: When filling the reactor cavity from the concensate storage tank and draining the reactor cavity to the condensate storage tank, the 30 foot limit does not apply provided there is a sufficient amount ot water to comp lete the flooding operation.

3. Primary containment integrity shal l be maintained at all times when the reactor is critical or when the reactor water temperature is above 212 F and fuel is in the reactor vessel except while performing lon power physics tests at atmospheric pressure during or af ter ref ueling at power levels not to exceec 5 Wt.

a) ' .' i t h one or more of the containment i sol at ion valves shown in i

Table 3.5.2 inoperable:

1. Maintain at least one isolation valve operable in each affected penetration that is open and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> fcr the traversing in-core probe systen) either; a) Restore the inoperab le val ve( s) to opercole status or b) Isolate each atfected penetratlon by use of at Ieast one I deactivoted automatic valve securea in tno isoIation  !

position, or c) Isolate each affected penetration by use of at least one closed manual valve or blind flange.

2. An inoperable contai nment isolation valve of the shutdown cooling system may be opened with a reator water temperature equal to or less than 350 F in order to place the reactor in the

3.5-lb cold shutdown condition. The inoperable valve shalI be returned to the operable status prior to placing the reactor in a condition where pritw y containment integrity is required.

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3.13-1 i

3.13 ACCIDENT MON! TORING INSTRUMENTATION Applicability: Applies to the operating status of accident monitoring instrumentation. i Objective: To assure operability of accident monitoring i n strumen tat ion .

Specification: A. R e l i e f V a l v,e,,oo,sition Indicators _

1. The accident monitoring instrumentation channels show in Tab l e 3.13.1 shall be operable when the mode switch is in the Startup or Run positions.

2. W I th the number of operable accident monitoring instru.nentation channel s less than the Total Number of Channels shown in Table 3.13.1, either restore the inoperable channel s to operable status w I thin 7 days, or place the reactor in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3. With the number of operable accident monitoring Instrumentation channels less than the Minimum Channels Operable requirements of Table 3.13.1, either restore the inoperable channel (s) to the operable s tatus s i thin 48 h >urs, or pl ace the reactor in the cold shutdown cond! tion wIthin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

s 3.13-2 J

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The operability of tre accident monitoring i n s tr u~ie n t a t i on ensures tnat sufficient information is available on selected plant parameters to noni tor anc access these variabies during and f o f lo ing an accident. This capsoility is consistent with 'lVREG 0578.

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3.I3-3 TABLE 3.13.1 ACCIDENT F10NITORING INSTRIMINTATION TOTAL NO. OF FilNIFtt!)1 CllANNiilS INSTRU51ENT CilANNEIS OPEllABI.fi

1. Itelief Valve Position Indicator (Primary Detector) 1/ valve 1/ valve or itelief Valve Position Indicator (Backup indications) 1/ valve

. 4.5-4 G. Continuous Leak Rate Monitor

1. When the prirnary con t a i nm eo ' is inerted the ::untain.nent shall be continuous 1 y mon i tored for gross leakage by revlew of the inerting system makeup requirements.

2. This monitoring system may be taken out of service for the purpose of naintenance or testing but snall be returned to service as soon as practical .

H. Report u. Test Results Each Integrated leakage rate test shall be the subject of a summary technical report, including results of the local leakage ra te tests . The repo-t shall int.! ude anal ysis and interpretation of the results which demonstrate compliance in meeting the speci f ied leak age rate limits.

I. Functional Tes of Valves ,

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1. All con ta i nm ent isolation valves specified in Table 3.5.2 shall be tested for automatic closure oy an isolation signal l I

during each ref ueling otuage. The following valves are required to close in the time specified below:

M.5in steam line isolation valves 3 3 sec. and e10 sec.  !

Isolation condenser isolation valves 660 sec.  !

Cleanup syste1 isolation v 31ves 660 sec . l Cleanup auxiliary pumps system isolation valves 660 sac. {

Shutdown >ys ten isolation valves SGO sec.

2. Each containrr.ent isolation valve shown in Table 3.5.2 shalI be demonstrated operable prior to returning the valve to service af ter maintenance, repair or replacement work is pertorined on the s 31/e y th s , ;oc i a M1 oc tua f y :>/ c/cl ing the v al ve through at feast one complete cycle of full travel and verifying the  !

i specified isolating time. Following maintenance, repair or replacement work on the control or power circui t for the valves show1 in T3ble 3.'i.2, Mn .s t 'ec te f conpanan t sh.311 'ae tested to a;;ure it will per rorm it s intended function in the circui t.

3. DJelng periods of sustained power operation each main steamline isolation valve shall be exercised in accordance with the fol low ing schedu le.

a. Dail y tests - E xerc i se valve (one at a time) to approximately 95f, open position with reactor at operation power level .

b. Quarterly tests - Trip valve (one at a time) and check full closure time, with reactor power not grea ter than 50%

o f r.s ted p3 pr .

. 4.13-1 4.13 ACCl0ENT MONITORING INST _R,UMENTATI]N, _

A pp 1,1 c_ab i l 1,t,y1 Appiles to surveliIance requirements for the accident noni toring instrumentation.

Objective: To verify the operability of the accident f monitoring instrumentation.  !

I Soecification: A. Relief Valve Position I ndicators i

1. E ach .iccident nioni toring :os h u nen ration i channel shalI be demonsteared operable by performance of the Channel Check I and Channel Calibration operations  !

at the f requencie shown in l Table 4.13.1.

Bases:

The aperabiiIty of the accident non i tor Ing instrumeq ration ensures -

that suf ficient Infornation is available on selected plant paraneters to monitor and assess these variables during and following an accident. This capability is consistent with NUREG 0578.

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4.13-2 .

TAftLE 4.13-1 ACCIDENT MONITORING INSTidlMENTATION Si1RVEILLANCE IlliQUIREMENTS ClIANNEL CllANNEL INSTRLIMiiNT CilECK CALIBRATION

1. Relief Valve Position Indicator (Primary Detector) A B Relief Valve Position Indicator (Backup indications) A B Legend:

A = at least once per 31 days; B = at leasc once per 18 months (550 days).

plant. A maximum of four years of tnis five year experience may be ful filled by related technical or academic training.

Shif t Tecnnical Advisor I

Requirements: Bachelor's degree or equivalent in a scientific or engineering discipline with specific training i n pl ant design, and response and analysis of the plant for transients and accidents.

6.3.2 Each member of the radiation protection organization for which there is a comparable position described in ANSI N18.1-1971 shall meet or exceed the minimum qual i fications speci f ied therein, or in the case of radiation protection technicians, they shall have at least one year's continuous experience in applied radiation protection work in a nucleaar f acil i ty desal i ng w i th radiological problems similar io those encountered in nuclear power stations, and shall have been certified by the Radiological Controls Manager, as qualified to perform assigned functions. This certification must be based on an NRC approved, documented program consisting of classroom training with appropriate examinations and documented positive findings by responsible superv ision that the i nd iv idual has demcnstrated his ability to perform each specified procedure and assigned function with an understanding of its basis and purpose.

6.4 TRAINING 6.4.1 A retraining program for operators shal I be maintained under the direction of the Manager, Training and shall meet the requirements ,

and recommendat ion of Appendix A of 10CFR Fart 55. Replacement '

tr a i n i ng programs, the content of which shall meet the requirements of 10CFR Part 55, shall be conducted under the direction of the Manager, Training for licensed operators and Senior Reactor ,

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l 6.4.2 )

l A training program for the Fire Brigade shal l be maintained under the direction of the Manager, Training.

6.5 SAFETY REVIEW AND AUDIT 1

The Director Oyster Creek Operations and three organizational units, l the Plant Operations Review Committee (PORC), the independent Safety )

Review Groups (lSRG) and the General 0 f f i ce Rev iew Board (GORB) )

f unction to accompl ish nuclear safety review and audit of the Oyster Creek Station.

6-2b

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9 6.5.1 Director Oyster Creek Operations (D000)

FU?1CT I ON 6.5.1.1 The Director Oyster Creek Operations shall ensure that:

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