ML20097A254

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Amend 107 to License NPF-39,changing TS in Response to Licensee Application
ML20097A254
Person / Time
Site: Limerick 
Issue date: 01/25/1996
From: Stolz J
Office of Nuclear Reactor Regulation
To:
Philadelphia Electric Co
Shared Package
ML20097A257 List:
References
NPF-39-A-107 NUDOCS 9602050226
Download: ML20097A254 (10)
v • d • e


Text

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1 UNITED STATES e

A NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2006&c001 PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-352 LIMERICK GENERATING STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE 1

Amendment No.107 License No. NPF-39 l

1.

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

A.

The application for amendment by Philadelphia Electric Company (the licensee) dated January 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 Commission's rules and 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 rules and regulations of the Commission; C.

There is reasonable assurance (1) that the activities authorized 1

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 regulatio,.;;

D.

The issuance of this amendment wi'.' not be inimical to the common defense and security or to the he.al..a and safety of the public; and j

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.

9602o50226 96o125 ADOCKOS00g2 1

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~ 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-39 is hereby amended to read as follows:

Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protectiop_ Plan contained in Appendix B, as revised through Amendment No. lu/

, 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 prior to startup in Cycle 7.

FOR THE NUCLEAR REGULATORY COMMISSION Jo n F. Stolz, Direct oject Directorate

-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

January 25, 1996

)

l

.. -. _ =...

ATTACHMENT TO LICENSE AMENDMENT NO.107 FACILITY OPERATING LICENSE NO. NPF-39 DOCKET NO. 50-111 l

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

INDEX i

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS SECTION PJfG1 REACTdRCOOLANTSYSTEM(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 CHAMBER...................................

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 Air 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 Suppres si on Pool Cool ing..............................

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

3/4 6-17 Table 3.6.3-1

- rM,ary Containment Isolation s.aiVes...........................

3/4 6-19 LIMERICK - UNIT 1 xii Amendment No. 33, 107

' CONTAINMENT SYSTEMS PRIMARY CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Primary containment leakage rates shall be limited to:

a.

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

b.

A combined leakage rate of less than or equal to 0.60 La 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 when pressurized to Pa, 44.0 psig.

c.

t d.

A combined leakage rate of less than or equal to 1 gpm times the total number of containment isolation valves in hydrostatically tested lines which penetrate the primary containment, when tested at 1.10 Pa, 48.4 psig.

APPLICABILITY: When PRIMARY CONTAINMENT INTEGRITY is required per Specification 3.6.1.1.

ACTION:

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, restore i

a.

The overall integrated leakage rate (s) to less than or equal to j

0.75 La, and I

I

l LIMERICK - UNIT 1 3/4 6-2 Amendment No. 107 i

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  • C0t"A;;iMENT S"S"EWS

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.I';;T..tG CONDL

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FOR OPERATION (Continued)

' ACTION:

(Continued) b.

The combined leakage rate for all penetrations and all valves listed j

in Table 3.6.3-1, except for main steam line isolation valves

  • and j

valves which are hydrostatically tested per. Table 3.6.3-1, subject to Type B and C tests to less than or equal to 0.60 La, and j

c.

The leakage rate to s11.5 scf per hour for any main steam isolation valve that exceeds 100 scf per hour, and restore the combined maximum pathway i

leakage to $200 scf per hour, and d.

The combined leakage rate for all containment isolation valves in I

hydrostatically tested lines which penetrate the primary containment to less than or equal to 1 gpm times the total number of such valves, prior to increasing the reactor coolant system temperature above 200"F.

j SURVEILLANCE REQUIREMENTS i

i 4.6.1.2 The primary containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR Part 50 using the methods and provisions of 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.**

b.

If any periodic Type A test fails to meet 0.75 L the test schedule for subsequent Type A tests shall be reviewed an$, approved by the Commission.

If two consecutive Type A tests fail to meet 0.75 La, 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 0.25La. The formula to be used is: [Lo + L s (Lo + Lam + leakage;] Lam - measured Typt A lea 0.25 La al test result; superimposed 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-

    • The interval between the second and third Overall Integrated Leakage Rate tests of the first 10-year service period will be extended to the sixth Unit I refueling outage.

As a result, the duration of the first 10-year service period will be extended to the end of the sixth Unit I refueling outage.

LIMERICK - UNIT 1 3/4 6-3 Anendment No. 67,107

CONTAINMENT SYSTEMS MSIV LEAKAGE ALTERNATE DRAIN PATHWAY l

UMITING_CQNDITION [gR OPERATION i

3.6.1.4 The MSIV Leakage Alternate Drain Pathway shall be OPERABLE.

l APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

With the MSIV Leakage Alternate Drain Pathway ino)erable, restore the pathway to OPERABLE status within 30 days or )e 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 RE0UIREMENTS 4.6.1.4 The MSIV Leakage Alternate Drain Pathway shall 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.

LIMERICK - UNIT 1 3/4 6-7 Amendment No. 71, 107

TABLE 3.6.3-1 PART A - PRIMARY CONTAIMENT ISOLATION VALVES 3

m L

5 1

Q INBOARD OUTBOARD ISOL.

I PENETRATION FUNCTION ISOLATION ISOLATION MAX.ISOL.

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

IF APP.

c$

(SEC)(26)

(20)

[

-4 003B CONTAINMENT INSTRUMENT 59-1005B (CK)

NA 59 i

GAS SUPPLY - HEADER 'B' HV59-1298 7

C,H,5

[

t 003D-2 CONTAIMENT INSTRUMENT 59-1112(CK)

NA GAS SUPPLY TO ADS VALVES HV59-151B 45 M

59 E&K t

t 007A(B,C,D)

MAIN STEAM LINE HV41-IF022A 5*

C,E,F,P,Q 6

41 l

'A'(B,C,D)

(B,C,D) 4 HV41-lF028A 5*

C,E,F,P,Q 6

l (B,C,D) l w

s

[

008 MAIN STEAM LINE DRAIN HV41-lF016 30 C,E,F,P,Q 4

41 HV41-1F019 30 C,E,F,P,Q

=

009A FEEDWATER 41-lF010A(CK)

NA 41 HV41-IF074A(CK)

NA 41-1036A(CK)

NA HV41-1308 45 HV41-133A 45 i

(

HV41-109A NA 32 i

a HV41-1F032A(CK)

NA

[

HV55-lF105 30 7

n HV44-lF039(CK)

NA j

(X-98) 41-1016(X-98, MA 31 X-44)

O 9

O l

I

TABLE 3.6.3-1 (Continued)

PART B - PRIMARY CONTAINMENT ISOLATION EXCESS FLOW CHECK VALVES C

z 3

INBOARD OUTBOARD ISOL.

p PENETRATION FUNCTION ISOLATION ISOLATION MAX.ISOL.

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

IF APP.

[

(SEC)(26)

(20) z Q

003A-1 INSTRUMENTATION

'D' XV41-1F070D 1

41 MAIN STEAM LINE FLOW XV41-lF073D 003A-2 INSTRUMENTATION

'A' XV43-lF003A 1

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

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

55 003D-1 INSTR.

'A' MAIN STEAM XV41-1F070A 1

41 LINE FLOW XV41-IF073A 007A(B,C,D)

INSTR.

'A'(B,C,D) MAIN (HV41-lF022A(B, 5*

C,E,F,P,Q 6

41

?

STEAM LINE PRESSURE C,0) SEE PART A (HV41-1F028A 5*

C,E,F,P,Q 6

THIS TABLE)

(8,C,D) 020A-1 INSTR - RPV LEVEL XV42-lF045B 1

42 020A-2 INSTR

'B' LPCI DELTA P XV51-1028 1

51 020A-3 INSTR

'D' LPCI DELTA P XV51-103B 1

51 0208-1 INSTR - RPV LEVEL XV42-IF045C 1

42 g:

0208-2 INSTR

'C' LPCI DELTA P XV51-102C 1

51

__________________u-;

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3/4.6 CONTAINMENT SYSTEMS BASES 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, 4

in conjunction with the leakage rate limitation, will limit the SITE BOUNDARY j

radiation doses to within the limits of 10 CFR Part 100 during accident conditions.

i 3/4.6.1.2 PRIMARY CONTAINMENT LEAKAGE i

j 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 s 44 psig, Pa. As an added conserva-tism, the measured overall integrated leakage rate is further limited to less 3

than or equal to 0.75 La during performance of the periodic tests to account for

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possible degradation of the containment leakage barriers between leakage tests.

4 l

Operating experience with the main steam line isolation valves has indicated that degradation has occasionally occurred in the leak tightness of j

the valves; therefore the special requirement for testing these valves.

l 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.

4 3/4.6.1.3 PRIMARY CONTAINMENT AIR LOCK The limitations on closure and leak rate for the primary containment air i

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 i

position during reactor o)eration. Only one closed door in the air lock j

is required to maintain tie integrity of the containment.

I 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 j

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 a

requirements have not always been continuously maintained. The requirement for j

the MSIV Leakage Alternate Drain Pathway serves to reduce the offsite dose, i

a LIMERICK - UNIT 1 B 3/4 6-1 Amendment No. 33, 106, 107

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