Text

Amends 118 & 81 to Licenses NPF-39 & NPF-85,respectively, Revising TS to Incorporate performance-based Testing IAW 10CFR50,app J
	ML20134B346
Person / Time
Site:	Limerick
Issue date:	01/24/1997
From:	Stolz J; Office of Nuclear Reactor Regulation
To:	; Philadelphia Electric Co
Shared Package
ML20134B349	List: ML20134B346; ML20134B351;
References
	NPF-39-A-118, NPF-85-A-081 NUDOCS 9701300046
	Download: ML20134B346 (30)
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UNITED STATES g-NUCLEAR RECULATORY COMMISSION f

WASHINGTON, D.C. 20N64001

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PHILADELPHIA ELECTRIC COMPANY DOCKET N0. 50-352 LIMERICK GENERATING STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 118 License No. NPF-39 1.

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

A.

The application for amendment by Philadelphia Electric Company (the licensee) dated June 28, 1996, as supplemented by letters dated November 4 and 5, and December 9,1996, 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; j

C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and j

safc+,y 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 common 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.

9701300046 970124 PDR ADOCK 0500 2

P E

i r

. 2.

Accordingly,thelicenseisamendedbychangesto{.icenseCondition2.D.

on page 7 of Facility Operating License No. NPF-39, and the license is also 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 Protection Plan contained in Appendix B, as revised through Amendment No. 118, 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/

y J

F. Stolz, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Attachments:

1.

Page 7 of License No. NPF-39 2.

Changes to the Technical Specifications Date of Issuance: January 24, 1997

Page 7 is attached, for convenience, for the composite license to reflect this change.

I j<

)

ATTACHMENT TO LICENSE AMENDMENT NO.118 FACILITY OPERATING LICENSE N0. NPF-39 DOCKET NO. 50-352 Replace the following pages of the License and Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

1.

Revise License as follows:

Remove Paae Insert Paae 7

7 2.

Revise Appendix A as follows:

Remove Paaes Insert Paaes i

3/4 6-1 3/4 6-1 i

3/4 6-2 3/4 6-2 3/4 6-3 3/4 6-3 3/4 6-4 3/4 6-4 3/4 6-5 3/4 6-5 3/4 6-6 3/4 6-6 4

3/4 6-8 3/4 6-8 3/4 6-14 3/4 6-14 B 3/4 6-1 B 3/4 6-1 B 3/4 6-2 B 3/4 6-2 6-14c i

I

3 l

~

g.

(14),Refuelina Floor Volume Connection to Standby Gas Treatment i

System (Section 6.2.3. SSER-2 and SSER-3)-

Prior to any movement of irradiated fuel within the refueling i

floor volume the licensee shall complete and test all modifi-cations required to connect the refueling floor volume to i

standby gas treatment system. During the interim period, the licensee shall not remove the reactor pressure vessel head l

prior.to the NRC staff review and approval.

(15)

Emeraency Plannina l

Procedures Sub_1ect to 44 CFR Part 350 i

l In the event the NRC finds that the lack of progress in comple-i.

tion of the procedures in the Federal Emergency Management Agency's final rule, 44 CFR Part 350, is an indication that a l

major substantive problem exists in achieving or maintaining an adequate state of emergency preparedness, the provisions of 10 CFR Section 50.54(s)(2) will apply.

D.

The facility requires exemptions from cortair, requirements of 1

10 CFR Part 50. These include (a) exemption from General Design Criteria (GDC) 61 of Appendix A, operation of that portion of the standby gas treatment system (SGTS) that serves the refueling area 4

l until the first refueling (Section 6.2.3 of SSER-2 and SSER-3), (b) exemption from GDC-56 of Appendix-A, the requirement for additional automatic containment isolation valves for the hydrogen recombiner lines and the requirement for automatic isolation of existing isolation valves in the Drywell Chilled Water (DCW) and the Reactor Enclosure Cooling Water (RECW) systems until prior to startup following the first refueling i

outage (Section 6.2.4.2 of the SER, SSER-1 and SSER-3), (c) exemption e

}

from GDC-19 of Appendix A, as related to the requirement for redundant remote shutdown capability (Section 7.4.2.3 of SSER-3 and SSER-5), (d) exemption from the requirement of Appendix J, the testing of containment air locks at times when the containment integrity is not required (Section 6.2.6.1 of the SER and SSER-3), (e) exemption from the requirements l

of Appendix J, the leak rate testing of the Main Steam Isolation Valves i

(MSIVs) at the peak calculated containment pressure, Pa, and exemption i

from the requirements of Appendix J that the measured MSIV leak rates be 1

included in the summation for the local leak rate test (Section 6.2.6 of SSER-3),

(f) exemption from the requirement of Appendix J, the local leak rate testing of s

the Traversing Incore Probe Shear Valves (Section 6.2.6 of the SER and SSER-3),

a (g) a one-time exemption from the requirement of Appendix J to perform local leak 4

4 Amendment No. 118

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~ 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT-PRIMARY CONTAINMENT INTEGRITY

- LIMITING CONDITION FOR OPERATION 3.6.1.1 PRIMARY CONTAINMENT INTEGRITY shall be maintained.

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

ACTION:

Without PRIMARY CONTAINMENT INTEGRITY, restore PRIMARY CONTAINMENT INTEGRITY within I hour or be in at least H0T SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD. SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

l

- SURVEILLANCE REQUIREMENTS 4.6.1.1 PRIMARY CONTAINMENT INTEGRITY shall be demonstrated:

a.

After each closing of each penetration subject to Type B testing, except the primary containment air locks, if opened following Type A or B test, by leak rate testing in accordance with the Primary Containment Leakage Rate Testing Program.

4 b.

At least once per 31 days by verifying that all primary containment 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 position, except as provided in Table 3.6.3-1 of Specification 3.6.3.

c.

By verifying the primary containment air lock is in compliance with i

the requirements of Specification 3.6.1.3.

d.

By verifying the suppression chamber is in compliance with the requirements of Specification 3.6.2.1.

See Special Test Exception 3.10.1

- 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 such verification need not be performed when the primary i

containment has not been deinerted since the last verification or more often than once per 92 days, i

4 LIMERICK - UNIT 1 3/4 6-1 Amendment No. 118 i

s CONTAINMENT SYSTEMS PRIMARY CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 5.6.1.2 Primary containment leakage rates shall be limited to:

a.

An overall integrated leakage rate (Type A Test) in accordance with the Primary Containment Leakage Rate Testing Program.

b.

A combined leakage rate in accordance with the Primary Containment Leakage Rate Testing Program 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.

c.

Less than or equal to 100 scf per hour through any one main steam isolation valve not to exceed 200 scf per hour for all four main steam lines, when tested at P 22.0 psig.

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 (Type A Test) exceeding the leakage rate specified in the Primary Containment Leakage Rate Testing Program, 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 the leakage rate specified in the Primary Containment Leakage Rate Testing Program, 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:

a.

The overall integrated leakage rate (s) (Type A Test) to be in accordance with the Primary Containment Leakage Rate Testing Program, and

Exemption to Appendix J of 10 CFR Part 50.

LIMERICK - UNIT 1 3/4 6-2 Amendment No. 497, 11E

00NIAINMENI SY5ItMS

' LIMITING CONDITION FOR OPERATION (Continued)

ACTION:

(Continued)

b. The 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 to be in accordance with the Primary Containment Leakage Rate Testing Program, and

c. The leakage rate to $11.5 scf per hour for any main steam isolation valve that exceeds 100 scf per hour, and restore the combined maximum pathway leakage to $200 scf per hour, and

d. The combined leakage rate for all containment isolation valves in 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.

SURVEILLANCE REQUIREMENTS 4.6.1.2 The primary containment leakage rates shall be demonstrated to be in accordance with the Primary Containment Leakage Rate Testing Program, or approved exemptions, for the following:

a.

Type A Test b.

Type B and C Tests (including air locks) c.

Main Steam Line Isolation Valves d.

Hydrostatically tested Containment Isolation Valves

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

LIMERICK - UNIT 1 3/4 6-3 Amendment No. 497, 118

s o

THIS PAGE IS INTENTIONALLY LEFT BLANK i

LIMERICK - UNIT 1 3/4 6-4 Amendment No. 2, 33, 71, 83, l

118 j

I CONTAINMENT SYSTEMS o

o

~

PRIMARY CONTAINMENT AIR LOCK LIMITING CONDITION FOR OPERATION-3.6.1.3 The primary containment air lock shall be OPERABLE with:

a.

Both doors closed except when the air lock is being used for normal j

transit entry and exit through the containment, then at least one l

air lock door shall be closed, and

)

b.

An overall air lock leakage rate in accordance with the Primary Containment Leakage Rate Testing Program.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2*, and 3.

ACTION:

1 a.

With one primary containment air. lock door inoperable:

i 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or lock the OPERABLE air lock door closed.

I 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.

i 3.

Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months l

and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

s 4.

The provisions of Specification 3.0.4 are not applicable.

j b.

With the primary containment air lock inoperable, except as a 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least H0T SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

i h

l j

See Special Test Exception 3.10.1.

J LIMERICK - UNIT 1 3/4 6-5 Amendment No. 33, 11C

~

i, CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS I

4.6.1.3 The primary containment air lock shall be demonstrated OPERABLE:

a.

By verifying the seal leakage rate is in accordance with the l

the Primary Containment Leakage Rate Testing Program.

j 4

b.

By conducting an overall air lock leakage test in accordance with the Primary Containment Leakage Rate Testing Program.

i c.

At least once per 6 months by verifying that only one door in the air lock can be opened at a time.***

i l

4 d

0 i.

l 1

}

(-

l I

i Except that the airlock doors need not be opened to verify interlock OPERA-3 BILITY when the primary containment is inerted, provided that the airlock j

doors' interlock is tested within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after the primary containment has i

been deinerted and provided the shield door to the airlock is maintained i

locked closed.

i LIMERICK - UNIT 1 3/4 6-6 Amendment No. 118

fo

', CONTAINMENT SYSTEMS PRIMARY CONTAINMENT STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.5 The structural integrity of the primary containment shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.5.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

-With the structural integrity of the primary containment not conforming to the above requirements, restore the structural integrity to within the limits within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS 4.6.1.5.1 The structural integrity of the exposed accessible interior and exterior surfaces of the primary containment, including the liner plate, shall be determined by a visual inspection of those surfaces.

This inspection shall

'be performed in accordance with the Primary Containment Leakage Rate Testing Program.

4.6.1.5.2 Reoorts Any abnormal degradation of the primary containment structure detected during the above required inspections shall be reported in a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days. This report shall include a description of the condition of the liner and concrete, the inspection procedure, the tolerances on cracking, and the corrective actions taken.

LIMERICK - UNIT 1 3/4 6-8 Amendment No. 118 i

CONTAINMENT SYSTEMS SUhVEILLANCE RE0VIREMENTS (Continued) c.

By verifying at least 8 suppression pool water temperature indicators in at least 8 locations, OPERABLE by performance of a:

1.

CHANNEL CHECK at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2.

CHANNEL FUNCTIONAL TEST at least once per 31 days, and 3.

CHANNEL CALIBRATION at least once per 24 months, with the temperature alarm setpoint for:

1.

High water temperature:

a) First setpoint s 95'F b) Second setpoint s 105 F c) Third setpoint s 110*F 4

d) Fourth setpoint s 120*F d.

By verifying at least two suppression chamber water level indicators OPERABLE by performance of a:

1.

CHANNEL CHECK at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , 2.

CHANNEL FUNCTIONAL TEST at least once per 92 days, and 3.

CHANNEL CALIBRATION at least once per 24* months, with the water level alarm setpoint for high water level 5 24'l-1/2" e.

Drywell-to-suppression chamber bypass leak tests shall be conducted to coincide with the Type A test at an initial differential pressure of 4 psi l

and verifying that the A/(k calculated from the measured leakage is within the specified limit.

If any drywell-to-suppression chamber bypass leak test fails to meet the specified limit, the test schedule for subsequent tests shall be reviewed and approved by the Commission.

If two consecutive tests fail to meet the specified limit, a test shall be performed at least every 24 months until two consecutive tests meet the specified limit, at which time the test schedule may be resumed.

f.

By conducting a leakage test on the drywell-to-suppression chamber vacuum breakers at a differential pressure of at least 4.0 psi and verifying that i

the total leakage area A/(k contributed by all vacuum breakers is less than or equal to 24% of the specified limit and the leakage area for an individual set of vacuum breakers is less than or equal to 12% of the specified limit. The vacuum breaker leakage test shall be conducted during j

each refueling outage for which the drywell-to-suppression chamber bypass j

leak test in Specification 4.6.2.1.e is not conducted.

The CHANNEL CALIBP.ATION for level transmitters LT-55-lN062B, -1N062F shall be

_ performed at least once per 18 months.

LIMERICK - UNIT 1 3/4 6-14 Amendment No. 68v-701-74 -408, 7

118

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, in conjunction with the leakage rate limitation, will limit the SITE B0UNDARY 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 design basis LOCA maximum peak containment pressure of s 44 psig, P..

As an added conservatism, the measured overall integrated leakage rate (Type A Test) 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 Primary Containment Leakage Rate Testing Program.

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 Testing Program.

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 l

Calculated doses resulting from the maximum leakage allowances for the main steamline isolation valves in the postulated LOCA situations will not i

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 fo' the MSIV Leakage Alternate Drain Pathway serves to reduce the offsite dose.

=

LIMERICK - UNIT 1 B 3/4 6-1 Amendment No. 33, 406.407, 3

118 4

CONTAINMENT SYSTEMS BASES l

3/4.6.1.5 PRIMARY CONTAINMENT STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment will be maintained comparable to the original design standards for the life of the unit. Structural integrity is required to ensure that the containment will withstand the maximum calculated pressure in the event of a LOCA.

A visual i

inspection in accordance with the Primary Containment Leakage Rate Testing Program is sufficient to demonstrate this capability.

3/4.6.1.6 DRYWELL AND SUPPRESSION CHAMBER INTERNAL PRESSURE The limitations on drywell and suppression chamber internal pressure ensure that the calculated containment peak pressure does not exceed the design pressure of 55 psig during LOCA conditions or that the external pressure differ-ential does not exceed the design maximum external pressure differential of 5.0 psid.

The limit of - 1.0 to + 2.0 psig for initial containment pressure will limit the total pressure to s 44 psig which is less than the design pressure and is consistent with the safety analysis.

3 f

3/4.6.1.7 DRYWELL AVERAGE AIR TEMPERATURE l

The limitation on drywell average air temperature ensures that the con-tainment peak air temperature does not exceed the design temperature of 340 F 1

during steam line break conditions and is consistent with the safety analysis.

3/4.6.1.8 DRYWELL AND SUPPRESSION CHAMBER PURGE SYSTEM The drywell and suppression chamber purge supply and exhaust isolation valves are required to be closed during plant operation except as required for i

inerting, deinerting and pressure control.

The 180 hours0.00208 days 0.05 hours 2.97619e-4 weeks 6.849e-5 months per 365 day limit on purge valve operation is imposed to protect the integrity of the SGTS filters.

Analysis indicates that should a LOCA occur while this pathway is being utilized, the associated pressure surge through the (18 or 24") purge lines will adversely affect the integrity of SGTS.

This limit is not imposed, however, on the subject valves when pressure control is being performed through the 2-inch bypass line, since a pressure surge through this line does not threaten the OPERABILITY of SGTS.

l e

d LIMERICK - UNIT 1 B 3/4 6-2 AmendmentNo. 29, 106, 115, 118

f ATINIFT TAT V E Q:$T LO.S PLCCEDL R ES hM1 MG iMS (Continued) g.

Primary Containment Leakaae Rate Testina Proaram 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, g

Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163

" Performance-Based Containment Leakage Test program," dated September 1995.

The peak calculated containment internal pressure for the design basis loss of coolant accident, P., is 44.0 psig.

The maximum allowable primary containment leakage rate, L, at P, shall be O.5% of primary containment air weight per day.

Leakage rate acceptance criteria are:

a.

Primary Containment leakage rate acceptance criterion is less than or equal to 1.0 L,.

During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are less than or equal to 0.60 L, for the Type B and Type C tests and less than or equal to 0.75 L, for Type A tests; j

b.

Air lock testing acceptance criteria are:

1)

Overall airlock leakage rate is less than or equal to 0.05 L.

i when tested at greater than or equal to P,.

2)

Seal leakage rate is less than or equal to 5 scf per hour when the gap between the door seals is pressurized to 10 psig.

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

The provisions of Specification 4.0.3 are applicable to the tests described in the Primary Containment Leakage Rate Testing Program.

2 1

1 LIMERICK - UNIT 1 6-14c Amendment No. 118 l

>@ '* h t

UNITED STATES p *i g

j NUCLEAR RESULATORY COMMISSION WASHINGTON, D.C. 20066-0001 "s...../

PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-353 LIMERICK GENERATING STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 81 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 June 28, 1996, as supplemented by letters dated November 4 and 5, and December 9, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 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 Comission's regulations; D.

The issuance of this amendment will not be inimical to the common 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 been satisfied.

G

. 2.

Accordingly, the license is amended by changes to License Condition 2.D.

on page 4 of Facility Operating License No. NPF-85*, and the license is also 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 4

The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 81

, are hereby incorporated in the license.

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

i 3.

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

FOR THE NUCLEAR REGULATORY COMMISSION r

M(

1 John 'F.

Stolz, Director Project Directorate I-2

)

Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Attachments:

1.

Page 4 of License No. NPF-85 2.

Changes to the Technical Specifications Date of Issuance: January 24, 1997 r

s i

Page 4 is attached, for convenience, for the composite license to reflect this change.

+

ATTACHMENT TO LICENSE AMENDMENT NO. 81 i

FACILITY OPERATING LICENSE NO. NPF-85 DOCKET NO. F0-353 Replace the following pages of the License and Appendix A Technical Sp,ecifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

4 1.

Revise License as follows:

]

Remove Paae Insert Paae 4

4 2.

Revise Appendix A as follows:

j Remove Paaes Insert Paaes 3/4 6-1 3/4 6-1 3/4 6-2 3/4 6-2 3/4 6-3 3/4 6-3 i

3/4 6-4 3/4 6-4 4

3/4 6-5 3/4 6-5 3/4 5-6 3/4 6-6 i

3/4 6-8 3/4 6-8 3/4 6-14 3/4 6-14 8 3/4 6-1 B 3/4 6-1 l

B 3/4 6-2 B 3/4 6-2 6-14c d

i F

_4 (4)

Physical Security and Safeauards The licensee shall fully implement and maintain in effect all provisions of the physical security, guard training and qualification and safeguards contingency plans previously approved by the Commission and all amendments and revisions to such plans made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled:

" Limerick Generating Station, Units 1 & 2, Physical Security Plan," with revisions submitted through October 31, 1988; " Limerick Generating Station, Units 1 & 2, Plant Security Personnel Training and Qualification Plan," with revisions submitted through October 1, 1985; and

" Limerick Generating Station, Units 1 & 2, Safeguards Contingency Plan," with revisions submitted through November 15, 1986.

D.

The facility requires exemptions from certain requirements of 10 CFR Part 50 and 10 CFR Part 70.

These include (a) exemption from the requirement of Appendix J, the testing of containment air locks at times when the containment integrity is not required (Section 6.2.6.1 of the SER and SSER-3), (b) exemption from the requirements of Appendix J, the leak rate testing of the Main Steam Isolation Valves (MSIVs) at the peak calculated containment pressure, Pa, and exemption from the requirements of Appendix J that the measured MSIV leak rates be included in the summation for the local leak rate test (Section 6.2.6.1 of SSER-3),

(c) exemption from the requirement of Appendix J, i

)

i i

Amendment No. 68, 81

3/4.6 CONTAINMENT SYSTEMS

' 3/4.6.1 PRIMARY' CONTAINMENT PRIMARY CONTAINMENT INTEGRITY M G CONDITION FOR OPERATION 3.6.1.1 PRIMARY CONTAINMENT INTEGP.ITY shall be maintained.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2*, and 3.

ACTION:

Without PRIMARY CONTAINMENT INTEGRITY, restore PRIMARY CONTAINMENT INTEGRITY within I hour or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE RE0VIREMENTS 4.6.1.1 PRIMARY CONTAINMENT INTEGRITY shall be demonstrated:

a.

After each closing of each penetration subject to Type B testing, except the primary containment air locks, if opened following Type A 1

or B test, by leak rate. testing in accordance with the Primary Containment Leakage Rate Testing Program, l

b.

At least once per 31 days by verifying that all primary containment penetrations ** not capable of being closed by 0PERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in position, except as provided in Table 3.6.3-1 of Specification 3.6.3.

c.

By verifying the primary containment air lock is in compliance with the requirements of Specification 3.6.1.3.

d.

By verifying the suppression chamber is in compliance with the requirements of Specification 3.6.2.1.

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See Special Test Exception 3.10.1

- 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 such verification need not be performed when the primary i

containment has not been deinerted since the last verification or more often than once per 92 days.

i LIMERICK - UNIT 2 3/4 6-1 Amendment No. 81

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CONTAINMENT SYSTEMS

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

a.

An overall integrated leakage rate (Type A Test) in accordance with the Primary Containment Leakage Rate Testing Program.

b.

A combined leakage rate in accordance with the Primary Containment Leakage Rate Testing Program 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.

c.

Less than or equal to 100 scf per hour through any one main steam isolation valve not to exceed 200 scf per hour for all four main steam lines, when tested at P, 22.0 psig.

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:

The measured overall integrated primary containment leakage rate a.

(Type A Test) exceeding the leakage rate specified in the Primary Containment Leakage Rate Testing Program, 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 the leakage rate specified in the Primary Containment Leakage Rate Testing Program, or i

c.

The measured leakage rate exceeding 100 scf per hour through any one 1

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:

The overall integrated leakage rate (s) (Type A Test) to be in accordance a.

with the Primary Containment Leakage Rate Testing Program, and

Exemption to Appendix J of 10 CFR Part 50.

l.IMERICK - UNIT 2 3/4 6-2 Amendment No. 53, 81

CONTAINMENT SYSTEMS LIM 111MG 10ND1Il0N_ EOR. 0PERATION (Conti nued)

ACTION:

(Continued)

b. The 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 to be in accordance with the Primary Containment Leakage Rate Testing Program, and

c. The leakage rate to $11.5 scf per hour for any main steam isolation valve that exceeds 100 scf per hour, and restore the combined maximum pathway leakage to $200 scf per hour, and

d. The combined leakage rate for all containment isolation valves in hydrostatically tested lines which penetrate the primary containment to less than or equal to I gpm times the total number of such valves, prior to increasing reactor coolant system temperature above 200*F.

SURVEILLANCE RE0VIREMENTS 4.6.1.2 The primary containment leakage rates shall be demonstrated to be in accordance with the Primary Containment Leakage Rate Testing Program, or approved exemptions, for the following:

a. Type A Test

b. Type B and C Tests (including air locks)

c. Main Steam Line Isolation Valves

d. Hydrostatically tested Containment Isolation Valves 1

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

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LIMERICK - UNIT 2 3/4 6-3 Amendment No. 53;-71, 81

s THIS PAGE IS INTENTIONALLY LEFT BLANK i

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

34 -44, 81 7

' CONTAINMENT SYSTEMS o

PRIMARY CONTAINMENT AIR LOCK LIMITING CONDITION FOR OPERATION 3.6.1.3 The primary containment air lock shall be OPERABLE with:

a. Both doors closed except when the air lock is being used for normal transit entry and exit through the containment, then at least one air lock door shall be closed, and

b. An overall air lock leakage rate in accordance with the Primary Containment j

Leakage Rate Testing Program.

J APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2*, and 3.

ACTION:

a. With one primary containment air lock door inoperable:

1.

Maintain at least the OPERABLE air lock door closed and either f

restore the inoperable air lock door to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 H0T SHUTOOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 4

and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4.

The provisions of Specification 3.0.4 are not applicable.

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b. With the primary containment air lock inoperable, except as a result 2

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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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See Special Test Exception 3.10.1.

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LIMERICK - UNIT 2 3/4 6-5 Amendment No. 81

> CONTAINMENT SYSTEMS SURVEILLANCE RE0UIREMENTS 4

4.6.1.3 The primary containment air lock shall be demonstrated OPERABLE:

a. By verifying the seal leakage rate is in accordance with the Primary Containment Leakage Rate Testing Program.

b. By conducting an overall air lock leakage test in accordance with the Primary Containment Leakage Rate Testing Program.

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c. At least once per 6 months by verifying that only one door in the air lock,can be opened at a time.***

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- - Except that the airlock doors need not be opened to verify interlock OPERA-BILITY when the primary containment is inerted, provided that the airlock doors' interlock is tested within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after the primary containment has been deinerted and provided the shield door to the airlock is maintained locked closed.

LIMERICK - UNIT 2 3/4 6-6 Amendment No. 81

CONTAINMENT SYSTEMS

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' PRIMARY CONTAINMENT STRUCTVRAL INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.5 The structural integrity of the primary containment shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.5.

APPLICABILITY-OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

With the structural integrity of the primary containment not conforming to the above requirements, restore the structural integrtty to within the limits within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE RE0VIREMENTS 4.6.1.5.1 The structural integrity of the exposed accessible interior and exterior surfaces of the primary containment, including the liner plate, shall be determined by a visual inspection of those surfaces.

This inspection shall be performed in accordance with the Primary Containment Leakage Rate Testing Program.

4.6.1.5.2 Reoorts Any abnormal degradation of the primary containment structure detected during the above required inspections shall be reported in a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days.

This report shall include a description of the condition of the liner and concrete, the inspection procedure, the tolerances on cracking, and the corrective actions taken.

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i LIMERICK - UNIT 2 3/4 6-8 Amendment No. 81

'[M IAINMENT SYSIfj$

'. SURVEILLANCE REQUIREMENTS (Continued)

c. By verifying at least 8 suppression pool water temperature indicators in at least 8 locations, OPERABLE by performance of a:

1. CHANNEL CHECK at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2. CHANNEL FUNCTIONAL TEST at least once per 31 days, and

3. CHANNEL CALIBRATION at least once per 24 months, with the temperature alarm setpoint for:

1. High water temperature:

a)

First setpoint s 95*F b)

Second setpoint s 105'F c)

Third setpoint s 110*F d)

Fourth setpoint s 120'F

d. By verifying at least two suppression chamber water level indicators OPERABLE by performance of a:

1. CHANNEL CHECK at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,

2. CHANNEL FUNCTIONAL TEST at least once per 92 days, and

3. CHANNEL CALIBRATION at least once per 24* months, with the water level alarm setpoint for high water level 5 24'l-1/2"

e. Drywell-to-suppression chamber bypass leak tests shall be conducted to coincide with the Type A test at an initial differential pressure of 4 psi and verifying that the A/(k calculation from the measured leakage is within the specified limit.

If any drywell-to-suppression chamber bypass leak test falls to meet the specified limit, the test schedule for subsequent tests shall be reviewed and approved by the Commission.

If two ccnsecutive tests fail to meet the specified limit, a test shall be performed at least every 24 months until two consecutive tests meet the specified limit, at which time the test schedule may be resumed.

f. By conducting a leakage test on the drywell-to-suppression chamber vacuum breakers at a differential pressure of at least 4.0 psi and verifying that the total leakage area A/(k contributed by all vacuum breakers is less than or equal to 24% of the specified limit and the leakage area for an individual set of vacuum breakers is less than or equal to 12% of the specified limit. The vacuum breaker leakage test shall be conducted during each refueling outage for which the drywell-to-suppression chamber bypass leak test in Specification 4.6.2.1.e is not conducted.

The CHANNEL CALIBRATION for level transmitters LT-55-2N062B, -2N062F shall be performed at least once per 18 months.

LIMERICK - UNIT 2 3/4 6-14 Amendment No. 3b-337-34 -7 7

81

d 3/4.6 CONTAINMENT SYSTEMS

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BASES 3/4.6.1 PRIMARY CONTAINMENT i

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 B0UNDARY 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 design basis LOCA maximum peak containment accident pressure of 44 psig, P..

As an added conservatism, the measured overall integrated leakage rate (Type A Test) 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 Primary Containment Leakage Rate Testing Program.

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 Testing Program. 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. 54r-53, 81

CONTAINMENT SYSTEMS

. BASES' 3/4.6.1.5 PRIMARY CONTAINMENT STRUCTVRAL INTEGRITY This limitation ensures that the structural integrity of the containment will be maintained comparable to the original design standards for the life of the unit. Structural integrity is required to ensure that the containment will withstand the maximum calculated pressure in the event of a LOCA. A visual 4

inspection in accordance with the Primary Containment Leakage Rate Testing Program is sufficient to demonstrate this capability.

3/4.6.1.6 DRYWELL AND SUPPRESSION CHAMBER INTERNAL PRESSURE i

1 The limitations on drywell and suppression chamber internal pressure ensure that the calculated containment peak pressure does not exceed the design pressure of 55 psig during LOCA conditions or that the external pressure differ-ential does not exceed the design maximum external pressure differential of 5.0 psid.

The limit of - 1.0 to + 2.0 psig for initial containment pressure will limit the total pressure to s 44 psig which is less than the design pressure and is consistent with the safety analysis.

I 3/4.6.1.7 DRYWELL AVERAGE AIR TEMPERATURE The limitation on drywell average air temperature ensures that the con-tainment peak air temperature does not exceed the design temperature of 340*F during steam line break conditions and is consistent with the safety analysis.

3/4.6.1.8 DRYWELL AND SUPPRESSION CHAMBER PURGE SYSTEM The drywell and suppression chamber purge supply and exhaust isolation valves are required to be closed during plant operation except as required for inerting, deinerting and pressure control.

The 180 hours0.00208 days 0.05 hours 2.97619e-4 weeks 6.849e-5 months per 365 day limit on purge valve operation is imposed to protect the integrity of the SGTS filters.

Analysis indicates that should a LOCA occur while this pathway is being utilized, the associated pressure surge through the (18 or 24") purge lines will adversely affect the integrity of the SGTS.

This limit is not imposed, however, on the subject

- valves when pressure co1 trol is being performed through the 2-inch bypass line, since a pressure surge through this line does not threaten the OPERABILITY of SGTS.

1 LIMERICK - UNIT 2 B 3/4 6-2 Amendment No. 54v-77, 81 1

'A[hINISTRATIVE CONTROLS j

o PROCEDURES AND PROGRAMS (Continued) g.

Primary Containment Leakaae Rate Testina Proaram 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 in accordance with the guidelines contained in Regulatory Guide 1.163

" Performance-Based Containment Leakage Test program," dated September 1995.

The peak calculated containment internal pressure for the design basis loss of coolant accident, P., is 44.0 psig.

The maximum allowable primary containment leakage rate, L, at P, shall be 0.5% of primary containment air weight per day.

Leakage rate acceptance criteria are:

a.

Primary Containment leakage rate acceptance criterion is less than or equal to 1.0 L,.

During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are less than or equal to 0.60 L, for the Type B and Type C tests and less than or equal to 0.75 L, for Type A tests; b.

Air lock testing acceptance criteria are:

1) Overall airlock leakage rate is less than or equal to 0.05 L, when tested at greater than or equal to P.

2) Seal leakage rate is less than or equal to 5 scf per hour when the gap between the door seals is pressurized to 10 psig.

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

The provisions of Specification 4.0.3 are applicable to the tests described 4

in the Primary Containment Leakage Rate Testing Program.

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LIMERICK - UNIT 2 6-14c Amendment No. 81

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ML20134B346

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