ML20099L714

Proposed Tech Specs 3/4.6.1.1 & 3/4.6.1.3,incorporating Option B of 10CFR50,App J

ML20099L714
Person / Time
Site:	Wolf Creek
Issue date:	12/20/1995
From:	WOLF CREEK NUCLEAR OPERATING CORP.
To:
Shared Package
ML20099L709	List: ML20099L706 ML20099L714
References
NUDOCS 9601020280
Download: ML20099L714 (6)

Text

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' Attachment IV to WO 95-0187

, Page 2 of 7 DEFINITIONS CONTAINMENT INTEGRITY 1.7 CONTAINMENT INTEGRITY shall exist when:

a. All penetrations required to be closed durir.g accident conditions are either:

1) Capable of being closed by an OPERABLE containment automatic isolation valve system, or

2) Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, except as provided in Table 3.6-1 of Specification 3.6.3.

b. All equipment hatches are closed and sealed,

c. Each air lock is in compliance with the requirements of l Specification 3.6.1.3,

d. The sealing mechanism associated with each penetration (e.g., welds, l bellows, or 0-rings) is OPERABLE, and

e. The containment leakage rates determined by Specification 444,44 4.6.1.1.c l are within the limits listed in the Bases of Specification l 3/4.6.1.1. j CONTROLLED LEAKAGE 1.8 CNTROLLED LEAKAGE shall be that seal water flow from the reactor coolant pump seats.

CORE ALTERATION 1.9 CORE ALTERATION shall be the movement or manipulation of any component  !

within the reactor vessel with the vessel head removed and fuel in the vessel.

Suspension of CORE ALTERATION shall not preclude completion of movement of a component to a safe conservative position.

CORE OPERATING LIMITS REPORT 1.10 The CORE OPERATING LIMITS REPORT (COLR)is the unit-specific document that provides core operating limits for the current operating reload cycle.

These cycle-specific core operating limits shall be determined for each reload cycle in accordance with Specification 6.9.1.9. Plant operation within these operating limits is addressed in individual Specifications.

WOLF CREEK - UNIT 1 1-2 Amendment No. 64,89 9601020290 951220 PDR ADOCK 05000482 P PDR

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Attachment IV to WO 95-0187

, Paga 3 of 7 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.

1 APPLICABILITY: MODES 1,2,3, and 4.

ACTION l Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within i hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:

a. At least once per 31 days by verifying that all penetrations

• not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except as provided in Table 3.6-1 of Specification 3.6.3;

b. By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3;

c. ^a ct cad c!O:ing Of e 2 penetration :ebjec* 10 Type 9 testing, except4he-containment O!r !00kt, 'f Opened fc!!0 wing : Type A Or 9 test, by !cek rate 100t!ng the Oce!"eith ga: et a precturemt4ess than P2,49 peig, and veriF/ing that when the4neasured !cakage rate for thecc ten!:!: Odded to the !cekage rate determined pursuant-to

, Specif!catien 4.6.1.1d. for !! Other Type 9 and C penetrationsr-the combined !cakage rate !: !ce: than 0.60 L,a;

'c. d. By performing containment leakage rate testingrexcept for conte;nment air 4eck4esting in accordance with 10 CFR 50, Amend:x J ;c mcygd v~nvy w-ry

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by approved exemptions; and the ContaIn'meritMaie' Rate Testing Program of Specification 6.8.4

d. e. By verifying containment structural integrity in accordance with the Containment Tendon Surveillance Program of Specification 6.8.5.c.

• Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed, or otherwise secured in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days.

WOLF CREEK- UNIT 1 3/4 6-1 Amendment No. 89 (Next page is 3/4 6-4)

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'Atta'chment IV to WO 95-0187 Page 4 of 7 l CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS l

LIMITING CONDITION FOR OPERATION 3.6.1.3 Each containment air lock shall be OPERABLE wgt'oth doors . ww%'

cloMxcepi'wherith'e alIloEs being used for normal transit and exits through the containment, then at least one air lock door shall be closed.

MW

. Both dcore c'ceed exceptwhe+the !r !cck i being eted for normal 4 rant!! entr/ nd ex!! thrcugh the centainment, then at ! cent one j aidock docr thc!! be c!cced, and l

b. ^ n evere!! !r !ce' !eckage rate of !e:: than er equ2! to 0.05 L a a4Sa' d B PE!9-6PPLICABILITY: MODES 1,2,3, and 4.

ACTION

a. With one containment air lock door inoperable:

1. Maintain at least the OPERABLE air lock door closed and either restore the inoperable air lock door to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or lock the OPERABLE air lock door closed.

2. Operation may then continue until performance of the next required overall air lock leakage test provided that the OPERABLE air lock door is verified to be locked closed at least once per 31 days,

3. Otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, and

4. The provisions of Specification 3.0.4 are not applicable

b. With the containment air lock inoperable, except as the result of an inoperable air lock door, maintain at least one air lock door closed; restore the inoperable air lock to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

WOLF CREEK - UMI' 1 3/4 6-4

'Atta'chment IV to WO 95-0187 Page 5 of 7 C.QNTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:

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( ,a. By verifying leakage rates in accordance with the Containment Leakage <

Rate Testing Program of Specification 6.8.41; and 1

-w.

a. W:!hin 72 heure fc!!cring e:d c!ccing, except when the n!r !cd ic being used fer me!!!p!c entries, then :t ! ::t once per 72 heur , by veri 8y!ng that the ten! !ede;e !: !et: than 0 0^5 Le at determined a me urement: when meceur-d for et ! cert 20 Seconde by pr-ci:icn cw

";ith the vc!ume bet;;::n 'he 00 !: et a constant precture Of greater l than er eque! to 10 p !g;  !

b. By conducting 4veralteir !cd !cd ge tect: O! not !ere than Pa, 48 p:!g, and ver!'ying the overa!! O!r !cd ! dege rete it within itsemit,

4) At !ce:t once per 6 monthe,# and

2) Prior Te estab!!:hing CONTA!N'A5NT-4.JTEGR!TY when meintenance h:: been pedermed on the !r !cd that cced Mfect the !

!cd sc !!ng cep2bi!ity *

b. e. At least once per 6 months by verif'f ngi that only one door in each air lock can be opened at a lime. 1

1. The prev! !cn: Of Sp-ci'ication 4.0 2 are not appkcabler

• This representsen4xemption to Appendix J, Peragrcph !!! O 2.(b)(44f

-40 CFR PaMC, WOLF CREEK - UNIT 1 3/4 6-5

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• ' Attachment IV to WO 95-0187

, Page 6 of 7 ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued)

8) Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Pert 50,  ;

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9) Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from lodine-131, lodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas beyond the SITE BOUNDARY conforming to Appendix 1 to 10 CFR Part 50,

10) Limitations on the annual dose or dose commitment to any MEMRER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

f. Badioloaical Environmental Monitorina Program A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) repre-sentative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways.

The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM. ,

2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and the modifications to the monitoring program are made if required by the results of this census, and

3) Participation in an Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

wvv v 6.8.5 a. Explosive Gas and Storage Tank Radioactivity Monitoring Program This program provides controls for potentially explosive gas mixtures contained in the WASTE GAS HOLDUP SYSTEM, the quantity of radioactivity contained in gas storage tanks, and the quantity of radioactivity contained in unprotected outdoor liquid storage tanks.

The program shal' include:

1. The limits for concentrations of hydrogen and oxygen in the WASTE GAS HOLDUP SYSTEM and a surveillance program to ensure the limits are maintained. 1

2. A surveillance program to ensure that the quantity of radioactivity contained in each gas storage tank is less than the amount that would result in a whole body exposure of 20.5 rem to any individualin an UNRESTRICTED AREA in the event of an uncontrolled release of the tank's WOLF CREEK UNIT 1 6-18 Amendment No. 42,89

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• • Attachment IV to WO 95-0187

. Page 7 of 7 l

INSERT *A" I l

i. Containment Leakage Rate Testing Program  !

A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be I in accordance with the guidelines contained in Regulatory Guide 1.163,

• Performance-Based Containment Leak-Test Program," dated September 1995.

The peak calculated containment internal pressure for the design basis ,

loss of coolant accident, P., is 48 psig.

The maximum allowable containment leakage rate, L., at P., shall be 1 0.20% of containment air weight per day.

Leakage rate acceptance criteria are:

a. Containment leakage rate acceptance criterion is s 1.0 L.. During ,

the first unit startup following testing in accordance with this l program, the leakage rate acceptance criteria are s 0.60 L, for l the Type B and C tests and s 0.75 L, for Type A tests; i l

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b. Air lock testing acceptance criteria are:

1) Overall air lock leakage rate is s 0.05 L, when tested at  ;

2 P. ; )

2) For each door, leakage rate is s 0.005 L, when pressurized to 2 10 psig.

The provisions of Technical Specification 4.0.2 do not apply to the test i frequencies specified in the Containment Leakage Rate Testing Program.

The provisions of Technical Specification 4.0.3 are applicable to the Containment Leakage Rate Testing Program.