ML20154A767

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Amends 112 & 101 to Licenses DPR-39 & DPR-48,respectively, Clarifying & Upgrading Tech Specs for Measuring Leakage Through Pressure Isolation Valves
ML20154A767
Person / Time
Site: Zion  File:ZionSolutions icon.png
Issue date: 04/15/1988
From: Muller D
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20154A754 List:
References
NUDOCS 8805160149
Download: ML20154A767 (10)
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f# '% UNITED STATES

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n NUCLEAR REGULATORY COMMISSION

$ .. j WASHINGTON, D. C. 20555

-e COMMONWEALTH EDISON COMPANY DOCKET N0. 50-295 ZION NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 112 License No. DPR-39

1. The Nuclear Regulatory Comission (the Comission) has found that:

A. The applications for amendment filed by the Comonwealth Edison j

Company (the licensee), dated November 13, 1987 and modified March 4,1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Comission; C. There is reasonable assurance: (1)thattheactivitiesauthorizedby this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D. The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been

__ satisfied.

2. Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the enclosure to this license amendment and para-

" graph 2.C.(2) of the Facility Operating License No. DPR-39 is hereby amended to read as follows:

8805160149 800415 PDR ADOCK 05000295 p PDR

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(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as ,

revised through Amendnent No.112 , are hereby incorporated in the l license. The licensee shall operate the facility in accordance with the '

Technical Specifications.

3. This amendment is effective as of the date of its issuance.

l FOR THE NUCLEAR REGULATORY COMMISSION Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, V and Special Projects

Enclosure:

Changes to the Technical Specifications Date of Issuance: April 15, 1988 i

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-[ g NUCLEAR REGULATORY COMMISSION

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l COMMONWEALTH EDIS0N COMPANY DOCKET N0. 50-304 ZION NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.101 License No. DPR-48

1. The Nuclear Regulatory Comission (the Comission) has found that:

! A. The application for amendment filed by the Comonwealth Edison i Company (thelicensee),datedNovember 13, 1987 and modified l l March 4, 1988, complies with the standards and requirements of i the. Atomic Energy Act of 1954, as amended (the Act), and the '

Comission's regulations set forth in 10 CFR Chapter I; )

B. The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Comission; C. There is reasonable assurance: (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations;

D. The issuance of this amendment will not be inimical to the coninon defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have baen satisfied.
2. Accordingly, the license is amended by changes to the Technical Specif1-Cations as indicated in the enclosure to this license amendment and para-graph 2.C.(2) of the Facility Operating License No. DPR-48 is hereby amended to read as follows: i

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(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.101, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III.

IV, V and Special Projects

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Enclosure:

Changes to the Technical Specifications Date of Issuance: April 15,1988 l

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l ATTACHMENT TO LICEi1SE AMENDMENTS

_ AMENDMENT NO.112FACILITY OPERATING LICENSE NO. DPR-39 AMENDMENT NO. 101 FACILITY OPERATING LICENSE N0. DPR-48 DOCKET NOS. 50-295 AND 50-304 Revise Appendix A as follows:

REMOVE INSERT viii viii 98a 98a 97a 97b.

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Operationa1 Modes 6b

) 1.1 1.2 Surveillance f requency Notation 6c 3.1-1 Reactor Protection System: limiting Operations Conditions and Setpoints 30 3.1 -2 Reactor Protection System Instrument Numbers ,. 33 3.3 '2-1 Zion Unit 1 Reactor Vess'el Toughness Data 88 3.3.2-2 Zion Unit 2 Reactor Vessel Toughness Data 89 3.3.3-1 Reactor Coolant Pressure Isolation Valves 97b a

3.3.4 -1 In Service Inspection Program 106

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3.3.5-1 Reactor Coolant Systems and Cheels,try Specifications 122 3.4 -1 Engineered Safeguards Actuation System-Limiting Conditions on 129 Operation and Setpoints 1 3.4-2 Engineered Safeguards System Instrument Numbers 132 Neutron Flux High Trip Points with Steam Generator Safety Valves 160a

! 3.7-1 1

j Inoperable - Four Loop Operation Neutron Flux High 1 rip Points with Steam Generator Safety Valves 160b 3.7-2 1 Inoperable - 1hree Loop Operation .

3.8.9-1 Accident Monitoring Instrumentation 192a Containment Isolation Valves - Phase A 205 . .

3.9 -3a ,

i Containment Isolation Valves - Phase 8 206 1 3.9-3b Containment Isolation Valves - Manually Operated 207 3.9-3c 3.9-3d Containment Isolation Valves - Other 207b -

Containment Isolation Valves - Main Steam Isolation Valves 208 j 3.9 -4 Maximum Permissible Concentration of Dissolved or Entrained Noble 226a l 3.11-1 Gases Releases from the Site to Unrestricted Areas in Liquid Effluents I

1 i LIST OF 1A8LES i

i i 11910 vill Amendment Nos. 112, 101 i ~

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LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.3.3.F REACTOR COOLANT SYSTEM PRESSURE ISOLATION 4.3.3.F REACTOR COOLANT SYSTEM PRESSURE ISOLATION WALVE LEAKAGE

- VALVE LEAKAGE Leakage through any Reactor Coolant System Each Reactor Coolant System Pressure Pressure Isolation Valve (PIV) shall be Isolation valve (PIV) shall be demenstrrted limited to that specified in Table 3.3.3-1. OPERABLE by demonstrating that its individual leakage is within its allowable limits as -

APPLICA81LITY: MODES 1, 2, 3 and 4. specified in Table 3.3.3-1:

ACTION: With any Reactor Coolant System Pressure a. At least once each REFUELING CYCLE.

Isolation Valve leakage above the limit, either b. Prior to entering MODE 2 whenever the  ;

plant has been in MODE 5 for 72 hcurs or

a. Reduce the leakage rate to within limits more and if leakage testing has not been within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or performed in the previous g months.
b. Isola'e the high pressure portion of the c. Prior to returning the valve to service affected system from the low pressure following maintenance, repair or portion within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by the use of at replacement work on the valve.

leas 2 other closed manual or Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or prior to entering deact3vated closed automatic or closed d.

check valves *, or MODE 2, following valve actuation where ,

flow through any of the PIVs results in

i. Be in at least MODE 3 within the next 6 water being injected into the Reactor hours zad MODE 5 within the following 30 Coolant System, test those valves that have experienced flow. (Exc1:41ng haurs.

MOV-RH8701 and MOV-RH8702.)

  • Amy check valve used for isolation shall be VERIFIED act to have exceeded their allowable leakage at their last performance test.

l TSC B7-11 Amendment Nos. 112, 101 19i on n ?i,n 97a

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Bases

3.3.3 1he total steam generator tube leakage llelt of ] GPM for all steamIgenerators ensures that the ~

i 4.3.3 dosage contribution f rom the tube leakage will be Ilmited to a small fraction of Part 100 limits in the event of either a steam generator tube rupture or steam Ilne break. 1he 1 GPM limit is  ;

j consistent with the assumptions used in the analysis of these accidents. The 500 gpd leakage 2

limit per steam generator ensures that steam generator ensures that steam generator tube integrity 15 maintained in the event of a main steam line rupture as under LOCA conditions. ** * ,

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j Pressure Isolation Valves (PtVs) are defined for each interface as any two valves in series within the Reactor Coolant System (RCS) pressure boundary,which separate the high pressure RCS from the j

attached low pressure systems. PIVs fall into two risk categories. The high risk PIVS are those whose gross failure could result in an Event V accident as identified in WASH-1400. "Reactor Safety Study". II.he Event V valves at Zion are ,1dentified as those valves that isolate the i

residual heat removal system (RNR) from the RCS. These valves represent a high risk because their j failure could lead to en overpressurization of The RHR piping and its subsequent failure. The  ;

failure of the RNR piping represents a high risk. factor in the eventual occurrence of core melt due to the inability to estabilsh recirculation from *he containment sump. It also represents a i higher risk because the rupture of the RNR piping results in a LOCA that bypasses the i

1 containment. The remaining PIVs are of a lower risk because they do not lead to a LOCA that

~ bypasses containment or that ruptures lower pressure piping. Leakage past these valves still constitutes a degradation of the RCS pressure boundary as defined in 10 CFR 50.2.

Periodic tests or verifications of the leak tight integrity of all pressure isolation valves are  ;

4 necessary in order to ensure the integrity of the RCS pressure boundary. The Survelliance '

Requirements for PIVs provides added insurance of valve integrity and thereby reduce the l

probability of an letersystem LOCA. -

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! ' 9Ba- Amendment Nos. 112. 101 l inst 0 i ..

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TABLE 3.3- .

REACTOR C0blANT SYSTEM PRL5 m g_ 150 tail 0N VALVES .-

Valve Allowable Leakage (b)

Valve Number Sire _ Function Sl9012A 2" Safety injection Cold Leg, toop A (a) 2" Safety injection Cold Leg, Loop 8 (a) ,.

5190128 -(a) 519012C 2" Safety injection Cold Leg, Loop C 2" Safety injection Cold Leg, Loop B (a)

  • 519012D (a) 519004C 2" Safety injection Hot Leg Loop B 2" Safety injection Hot Leg, Loop C (a) 519004D (a) 5189059 4" Safety, Injection Hot Leg, Loop A g

4" Safety injection Hot Leg, Loop D (a)

Sl8905A (a)

Sl9001A 8" RHR/ Safety injection Cold Leg, Loop 8 8" RHR/ Safety injection Cold Leg Loop C (a) 5190018 (a) 519001C 8* RHR/ Safety injection Cold Leg, Loop D 8" RHR/ Safety injection Cold Leg. Loop A (a) 5190010 (a) 518949C 8" Safety injection Hot Leg, Loop B 8" Safety injection Hot Leg, Loop C (a) 518949D (a)

RH8949A 8" RHR/ Safety injection Hot Leg, Loop A 8" RHR/ Safety injection Hot Leg, Loop B (a)

RH89498 (a) 8" Residual Heat Removal Cold Leg, Loop 8 Sl9002A Residual Heat Removal Cold Leg. Loop C (a) 5190028 8" 8" Residual Heat Removal Cold Leg, Loop D (a)

SI9002C Residual Heat Removal Cold Leg, Leop A (a)

SI9002D 8" 8" Residual Heat Removal Hot Leg, Loop A (a)

RH8736A (a) 8" Residual Heat Removal Hot Leg Loop D RH87368 (a) 10" Accumulator A Cold Leg, Loop A 518948A Accumulator C Cold Leg, Loop C (a) -

5189488 10" 10" - Accumulator D Cold Leg. Loop D (a) 518948C Accumulator 8 Cold Leg, Loop 8 (a) 518948p 10" 10" Accumulator A Cold Leg. Loop A (a) 518956A Accumulator- C Cold Leg, Loop C (a)

MOV-RH8701 Residual Heat Removal Suction. Loop A (a)

MOV-RH8702 14" (N01LS PERI AINING 101HL TABLE APPLAR ON FOLLOWING PAGE!)

97b Amendment Nos. 112, 101 11910 .

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Notes for Table 3.3.3-1:

1 (a) Allowable Leakage _ Rates

1.) thakageratesithan1.0gpmareacceptable. '
2.) Leakage rates > 1.0 gem but $ 5.0 gpm are acceptable if the latest measured rate has not exceeded the rate determined by the previous test by an amount that reduces the margin between measured J

leakage rate and the maximum leakage rate of 5.0 gpa by 1 50%.

7' 3.) Leakage rates > 1.0 gym but S 5.0 sps are unacceptable if the latest measured leakage rate exceeds the rate determined by the previous test by an amount that reduces the margin between measured l

1eakage rate and the maximum leakage rate of 5.0 gpa by 2 50%.

! 4.) Leakage rates > 5.0 gpa are unacceptable.

(b) Test Conditions 1.) Test differential pressure sha!1 not be < 150 psid.

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'IC Amendment Nos. 112, 101

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