ML20080J865

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Amend 53 to License NPF-85,permiting Increase in Allowable Leak Rate for Main Steam Isolation Valves & Deleting MSIV Leakage Control Sys
ML20080J865
Person / Time
Site: Limerick 
Issue date: 02/16/1995
From: Stolz J
Office of Nuclear Reactor Regulation
To:
Philadelphia Electric Co
Shared Package
ML20080J867 List:
References
NPF-85-A-053 NUDOCS 9502280146
Download: ML20080J865 (10)
v • d • e


Text

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UNITED STATES g

j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2006H001

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PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-353 LIMERICK GENERATING STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.53 License No. NPF-85 1.

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

A.

The application for amendment by Philadelphia Electric Company (the licensee) dated Anuary 14, 1994, as supplemented by letters dated August 1, October 25, December 13, December 22, 1994 (two submittals) and February 7,1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations sat forth in 10 CFR Chapter I; 8.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (i) 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 Commission'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.

9502280146 950216 PDR ADOCK 05000353 P

PDR

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.1

q 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-85 is hereby amended to read as follows:

Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 53

, are hereby incorporated into this license.

Philadelphia Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION b F. Stolz, Dire tor oject Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: February 16, 1995

s-e ATTACHMENT TO LICENSE AMENDMENT NO. 53 FACILITY OPERATING LICENSE NO. NPF-85 DOCKET NO. 50-353 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.

Remove Insert xii xii 3/4 6-2 3/4 6-2 3/4 6-3 3/4 6-3 3/4 6-7 3/4 6-7 3/4 6-19 3/4 6-19 3/4 6-31 3/4 6-31 B 3/4 6-1 B 3/4 6-1

O INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE REACTOR COOLANT SYSTEM (Continued)

~3/4.4.9 RESIDUAL HEAT REMOVAL Hot Shutdown............................................

3/4 4-25 Cold Shutdown...........................................

3/4 4-26 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ECCS - 0PERATING........................................

3/4 5-1 3/4.5.2 ECCS - SHUTD0WN.........................................

3/4 5-6 3/4.5.3 SUPPRESSION CHAM 8ER.....................................

3/4 5-8 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Primary Containment Integrity...........................

3/4 6-1 Primary Containment Leakage.............................

3/4 6-2 Primary Containment Air Lock............................

3/4 6-5 MSIV Leakage Alternate Drain Pathway....................

3/4 6-7 Primary Containment Structural Integri ty................

3/4 6-8 Drywell and Suppression Chamber Internal Pressure.......

3/4 6-9 Drywell Average Ai r Temperature.........................

3/4 6-10 Drywell and Suppression Chamber Purge System............

3/4 6-11 3/4.6.2 DEPRESSURIZATION SYSTEMS Suppression Chamber.....................................

3/4 6-12 Suppression Pool Spray..................................

3/4 6-15 Suppression Pool Cooling................................

3/4 6-16 3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES....................

3/4 6-17 Table 3.6.3-1 Primary Containment Isolation Va1ves..........................

3/4 6-19 LIMERICK - UNIT 2 xii Amendment No. 53

7 _

' CONTAINMENT SYSTEMS PRIMARY CONTAINMENT LEAKAGE lLIMITINC CONDITION FOR OPERATION

-i 3.6.1.1 Primary containment. leakage rates shall be limited to:

l a

a.

An overall integrated leakage rate of less than or equal to i

La, 0.500 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at Pa, 44.0 psig.

l b.

A combined leakage rate of less than or equal to 0.60 La for all-3 penetrations and all valves listed in Table 3.6.3-1, except for main i

steam line' isolation valves

  • and valves which are hydrostatically-tested per Table 3.6.3-1, subject to Type B and C tests when pressurized to Pa, 44.0 psig.

c.

t d.

A combined leakage rate of less than or equal to 1 gpm times the

.j total number of containment isolation valves in hydrostatically tested lines which penetrate the primary containment, when tested at 1.10 Pa, 48.4 psig.

1 APPLICABILIII: When PRIMARY CONTAINMENT INTEGRITY is required per-Specification 3.6.1.1.

ACTION:

l With:

a.

The measured overall integrated primary containment leakage rate exceeding 0.75 La, or b.

The measured combined leakage rate for all penetrations.and all valves listed in Table 3.6.3-1, except for main steam'line isolation valves

  • and valves which are hydrostatically tested per Table 3.6.3-1, subject to Type B and C tests exceeding 0.60 La, or c.

The measured leakage rate exceeding 100 scf per hour through any one main steam isolation valve, or exceeding 200 scf per hour for all four main steam lines, or d.

The measured combined leakage rate for all containment isolation valves in hydrostatically tested lines which penetrate the primary containment exceeding'1 gpm times the total number of such valves, j

restore:

a.

The overall integrated leakage rate (s) to less than or equal to 0.75La, and j

  • Exemption to Appendix J of 10 CFR Part 50.

LIMERICK.- UNIT 2 3/4 6-2 Amendment No. 53 o.

L

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NCONT[INMENTLSYSTEMS

~ LIMITING CONDITION FOR OPERATION (Continued)

ACTION:

-(Continued)~

b.

The c6mbined leakage rate for all penetrations and all valves listed in Table 3.6.3-1, except for main steam line isolation valves

  • and valves which are hydrostatically tested per Table 3.6.3-1, sub;!act i

+

to Type B and C tests to less thar, or equal to 0.60 La, and c.

The leakr rat'e to $11.5 scf per hour-for any main steam isolation valve i

that exc_.Js 100 scf per hour, and restore the combined maximum pathway l

1eakage to s200 scf per hour, and d.

The combined leakage rate for all containment isolation valves in q

hydrostatically tested lines which penetrate the primary containment 1

to less than or equal to 1 gpm times the total number of such valves, j

prior to increasi.ng reactor coolant system temperature above 200*F.

SURVEILLANCE RE0VIREMENTS 4.6.1.2 The primary containment leakage rates shall be demonstrated :at the j

'following test schedule and shall be determined in conformance with the criteria i

specified in Appendix J of 10 CFR Part 50 using the methods and provisions of

.I l

ANSI 45.4 1972 and BN-TOP-1 and verifying the result by the Mass Point Methodology described in ANSI N56.8-1981:

.a.

Three Type A Overall Integrated Containment Leakage Rate tests shall be conducted at 40 10 month intervals during shutdown at Pa, 44.0 psig, during each 10-year service period. The third test of each set shall be conducted during the shutdown for the 10-year plant inservice inspection, i

b.

If any periodic Type A test fails to meet.0.75 La, the test schedule

.l for subsequent Type A tests shall be reviewed and approved by the Commission.

If two consecutive Type A-tests fail to meet 0.75 La.

I a Type A test shall be performed at least every 18 months until two consecutive Type A tests meet 0.75 La, at which time the above test schedule may be resumed.

c.

The accuracy of each Type A test shall be verified by a supplemental test which:

1.

Confirms the accuracy of the test by verifying that the difference between the supplemental data and the Type A test data is within 0.25 La. The formula to be used is: {Lo + Lam -0.25 Lal 5 Lc s [Lo + Lam + 0.25 La] where Lc - supplemental test result; to -

superimposed leakage;_ Lam - measured Type A leakage.

2.

Has duration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental test.

3.

Requires the quantity of gas injected into the containment or bled from the containment during the supplemental test to be between 0.75 La and 1.25 La-

  • Exemption to Appendix "J" to 10 CFR Part 50.

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i i

LIMERICK - UNIT 2 3/4 6-3 Amendment No. 53 J

l o

4.

fatiTAINMENT SYSTEMS MSIV LEAKAGE ALTERNATE DRAIN PATHWAY l

LIMITING CONDITION FOR OPERATION 3.6.1.4 The MSIV Leakage Alternate Drain Pathway shall be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

' With the MSIV Leakage Alternate Drain Pathway inoperable, restore the pathway to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE RECUIREMENTS 4.6.1.4 The MSIV Leakage Alternate Drain Pathway sha'il be demonstrated OPERABLE:

a.

In accordance with 4.0.5, by cycling each motor operated valve, required to be repositioned, through at least one complete cycle of full travel.

tIMERICK - UNIT 2 3/4 6-7 Amendment No. 34, 53

TABLE 3.6.3-1 PART A - PRIMARY CONTAllmENT ISOLATiMJhJLi E

z9 INBOARD OUTBOARD ISOL.

E PENETRATION FUNCTION ISOLATION ISOLATION MAX.ISOL.

SIGNAL (S), NOTES P&ID NUMBER BARRIER BARRIER TIME.IF APP.IF APP.

~

(SEC)(26)

(20)

E Z

0038 CONTAIMENT INSTRUMENT-59-2005B (CK)

NA 59 m

GAS SUPPLY - HEADER 'B' HV59-2298 7

C,H,S 0030-2 CONTAIMENT INSTRUMENT 59-2112(CK)

NA GAS SUPPLY TO ADS VALVES HV59-2518 45 M

59 E&K 007A(B,C,D)

MAIN STEAM LINE HV41-2F022A 5*

C,E,F,P,Q 6

41

'A'(B,C,D)

(B,C,D)

HV41-2F028A 5*

C,E,F,P,Q 6

i (8,C,D) 008 MAIN STEAM LINE DRAIN HV41-2F016 30 C,E,F,P,Q 4

41 HV41-2F019 30 C,E,F,P,Q 3

e 009A FEEDWATER 41-2F010A(CK)

NA 41 HV41-2F074A(CK)-

NA t

41-2036A(CK)

NA HV41-2308 45 HV41-?33A 45 HV41-209A NA 32 y

HV41-2F032A(CK)

NA 8

HV55-2F105 30 7

D HV44-2F039(CK)

NA k

(X-98)

E 41-2016(X-98, MA 31 z

X-44)

P t

W

TABLE 3.6.3-1 (Continued)

PART B - PRIMARY CONTAllmENT ISOLATION EXCESS FLOW CHECK VALVES C

z9 M

INBOARD OUTBOARD ISOL.

PENETRATION FUNCTION ISOLATION

. ISOLATION MAX.ISOL.

SIGNAL (S),

NOTES P&ID NUMBER BARRIER BARRIER TIME.IF APP. IF APP.

E (SEC)(26)

(20)

_w 003A-1 INSTRUNENTATION

'D' XV41-2F0700 1

41 m

MAIN STEAM LINE FLOW XV41-2F0730 i

003A-2 INSTRUMENTATION

'A' XV43-2F003A 1

43 RECIRC PUNP SEAL PRESSURE 003C-1 INSTR. - HPCI STEAM FLOW XV55-2F024A 1

55 003C-2 INSTR. - HPCI STEAM FLOW XV55-2F024C 1

55 t'

0030-1 INSTR.

'A' MAIN STEAM XV41-2F070A 1

41 LINE FLOW XV41-2F073A i0 007A(B,C,D) INSTR.

'A'(B,C,D) MAIN (HV41-2F022A(B, 5*

C,E,F,P,Q 6

41 STEAM LINE PRESSURE C,D) SEE PART A (HV41-2F028A 5*

' C,E,F,P,Q 6

THIS TABLE)

(B,C,0)

XV42-2F0458 1

42 020A-1 INSTR - RPV LEVEL XV51-2028 1

51 020A-2 INSTR

'B' LPCI DELTA P 1

XV51-203B 1

51 020A-3 INSTR

'D' LPCI DELTA P XV42-2F045C 1

42 g:

020B-1 INSTR - RPV LEVEL 0208-2 INSTR

'C' LPCI DELTA P XV51-202C 1

51 0

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'3/4.6 CONTAINMENT SYSTEMS BASES j

3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 PRIMARY CONTAINMENT INTEGRITY PRIMARY CONTAINMENT INTEGRITY ensures that the release of radioactive mate-rials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the safety analyses. This restriction, in conjunction with the leakage rate limitation, will limit the SITE BOUNDARY radiation doses to within the limits of 10 CFR Part 100 during accident conditions.

3/4.6.1.2 PRIMARY CONTAINMENT LEAKAGE The limitations on primary containment leakage rates ensure that the total containment leakage volume will not exceed the value calculated in the safety analyses for the peak accident pressure of 5 44 psig, P. As an added conserva-tism, the measured overall integrated leakage rate is further limited to less than or equal to 0.75 L during performance of the periodic tests to account for possible degradation of the containment leakage barriers between leakage tests.

Operating experience with the main steam line isolation valves has indicated that degradation has occasionally occurred in the leak tightness of the valves; therefore the special requirement for testing these valves.

The surveillance testing for measuring leakage rates is consistent with the requirements of Appendix J of 10 CFR Part 50 with the exception of exemptions granted for leak testing of the main steam isolation valves, the airlock and TIP shear valves.

3/4.6.1.3 PRIMARY CONTAINMENT AIR LOCK The limitations on closure and leak rate for the primary containment air lock are required to meet the restrictions on PRIMARY CONTAINMENT INTEGRITY and the primary containment leakage rate given in Specifications 3.6.1.1 and 3.6.1.2.

The specification makes allowances for the fact that there may be long periods of time when the air lock will be in a closed and secured position during reactor operation. Only one closed door in the air lock is required to maintain the integrity of the containment.

3/4.6.1.4 MSIV LEAKAGE ALTERNATE DRAIN PATHWAY Calculated doses resulting from the maximum leakage allowances for the main steamline isolation valves in the postulated LOCA situations will not exceed the criteria of 10 CFR Part 100 guidelines, provided the main steam line system from the isolation valves up to and including the turbine condenser remains intact. Operating experience has indicated that degradation has occasionally occurred in the leak tightness of the MSIVs such that the specified leakage requirements have not always been continuously maintained.

The requirement for the MSIV Leakage Alternate Drain Pathway serves to reduce the offsite dose.

LIMERICK - UNIT 2 B 3/4 6-1 Amendment No. H, 53 l

.

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