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Amend 161 to License DPR-35,re Changes to Listed TS & Addition of Sections 3.7.B.1.f & 3.7.B.2.e to Require That Both Trains of Standby Gas Treatment & CR Air Filtration Sys Operable
	ML20081H894
Person / Time
Site:	Pilgrim
Issue date:	03/22/1995
From:	Marsh L; Office of Nuclear Reactor Regulation
To:	;
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ML20081H895	List: ML20081H894; ML20081H897;
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	NUDOCS 9503240426
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1-UNITED STATES l

.j NUCLEAR REGULATORY COMMISSION i

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~t WASHINGTON, D.C. 20566-0001 s...../

l BOSTON EDISON COMPANY DOCKET NO. 50-293 PILGRIM NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE i

Amendment No.

161 License No. DPR-35 1.

The Nuclear Regulatory Comission (the Commission or the NRC) has found that:

A.

The application for amendment filed by the Boston Edison Company (the licensee) dated September 6,1994, as supplemented February 15, 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; B.

The facility will operate in conformity with the application, the i

provisions of the Act, and the rules and regulations of the i

Comission; C.

There is reasonable assurance:

(i) that the activities authorized by this amendment can be conducted without endangering the health and ssiety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; i

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 Comission's regulations and all.-applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment.

9503240426 950322 PDR ADOCK 05000293 P

PDR

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3.

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

FOR THE NUCLEAR REGULATORY COMMISSION l

ejdbledyardB. Marsh, Dire'or=

l Project Directorate I-l Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation l

Attachment:

Changes to the Technical Specifications Date of Issuance:

March 22,1995 i

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ATTACHMENT TO LICENSE AMENDMENT NO. 161 FACILITY OPERATING LICENSE NO. DPR-35 DOCKET NO. 50-293 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 area of change.

j Remove Insert 3/4.7-11 3/4.7-11 3/4.7-12 3/4.7-12 3/4.7-13 3/4.7-13 3/4.7-14 3/4.7-14 3/4.7-15 3/4.7-15 3/4.7-16 3/4.7-16 3/4.7-17 3/4.7-17

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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 3.7 CONTAINMENT SYSTEMS (Cont) 4.7 CONTAINMENT SYSTEMS (Cont)

A.

Primary Containment (Cont)

With no H2 analyzer operable, reactor operation is allowed for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

If one of the inoperable analyzers is not made fully operable within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , the reactor shall be in a least Hot Shutdown within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

B.

Standby Cas Treatment System and B.

Standby Cas Treatment System and Control Room High Efficiency Air Control Room High Efficiency Air Filtration System Filtration System

1. Standby Cas Treatment System

a. Except as specified in gg 3.7.B.1.c or 3.7.B.1.f below, both trains of the Perating cycle, it shall be demonstrated that standby gas treatment system Pressure drop across the and the diesel generators ca ed W e N ency required for operation of filters and charcoal such trains shall be ads rber banks is less operable at all times when than 8 inches of water at secondary containment 4000 cfm.

integrity is required or the reactor shall be shutdown in

2. At least once per

"#8' operating cycle, dem nstrare that the

b. 1. The results of the in-place cold DOP tests on train 8re Perable and HEPA filters shall show are C8Pable of an output 2994 DOP removal. The results of halogenated hydrocarbon tests on

3. The tests and analysis of charcoal adsorber banks Specification 3.7.B.1.b.

shall show2994 shall be performed at halogenated hydrocarbon least once per operating

- - "*I*

cycle or following painting, fire or chemical release in any ventilation zone communicating with the system while the system is operating that could contaminate the HEPA filters or charcoal adsorbers.

4. At least once per operating cycle, automatic initiation of Amendment No. 15,-42,- 50 r - Sir 112 -144r -151,161 3/4.7-11 1

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LIMITING CONDITIONS FOR OPERATION SUR7EILLANCE REOUIREMENTS 3.7 CONTAINMENT SYSTEMS (Cont) 4.7 CONTAINMENT SYSTEMS (Cont)

B.

Standby Gas Treatment System and B.

Standby Gas Treatment System and Control Room Hirh Efficiency Air Control Room Hich Efficiency Air Filtration System (ront)

Filtration System (Cont)

2. The results of the each branch of the laboratory carbon sample standby gas treatment anal sis shall show295%

system shall be nethyl iodide removal at demonstrated, with a velocity within 10% of Specification 3.7.B.1.d system design, 0.5 to 1.5 satisfied.

3 mg/m inlet methyl iodide concentration, 270% R.H.

5. Each train of the standby anda190*F. The analysis gas treatment system results are to be shall be operated for at verified as acceptable least 15 minutes per within 31 days after month.

sample rsmoval, or declare that train

6. The tests and analysis of inoperable and take the Specification 3.7.B.1.b.2 actions specified shall be performed after 3.7.B.1.c.

every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of system operation.

c From and after the date that one train of the Standby Gas

b. 1. In-place cold DOP testing Treatment System is made or shall be performed on the found to be inoperable for HEPA filters after each any reason, except as completed or partial specified in 3.7.B.l.f replacement of the HEPA below, continued reactor filter bank and after any operation, irradiated fuel structural maintenance on handling, or new fuel the HEPA f}1ter system handling over spent fuel housing which could pool or core is permissible affect the HEPA filter only during the succeeding bank bypass leakage.

seven days providing that within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months all active

2. Halogenated hydrocarbon components of the other testing shall be standby gas treatment train performed on the charcoal shall be demonstrated to be adsorber bank after each operable.

partial or complete replacement of the charcoal adsorber bank or after any structural maintenance on the charcoal adsorber housing which could affect the charcoal adsorber bank bypass leakage.

6 Amendment No. 42,-50,-51,-112,-144,161 3/4.7-12

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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 3.7 CONTAINMENT SYSTEMS (Cont) 4.7 CONTAINMENT SYSTEMS (Cont)

B.

Standby Gas Treatment System and B.

Standby Gas Treatment System and i

Control Room Hirh Efficiency Air Control Room High Efficiency Air Filtration System (Cont)

Filtration System (Cont)

d. Fans shall operate within i 10% of 4000 efs.

i e Except as specified in l

3.7.B.l.c or 3.7.B.l.f. both trains of the Standby Cas Treatment System shall be i

operable during irradiated fuel handling, or new fuel handling over the spent fuel pool or core. If the system is not operable, fuel movement shall not be started. Any fuel assembly movement in progress may be completed, i

f.

During refueling, one train of the Standby Cas Treatment System can be without its safety-related bus and/or emergency diesel generator without entering the LCO action statement provided the following conditions are met:

Fuel movement will not occur until five days following reactor shutdown.

Prior to and during fuel movement, the SB0 D/G or the Shutdown Transformer is required to be operable and capable of supply power to the emergency bus.

Fuel movement will not occur until the reactor vessel is flooded up to elevation 114'.

The train of SGTS without its safety related bus or without is emergency diesel generator will have power supplied from a normal offsite source via a non sa fety-related bus. The normal offsite source consints of either the Startup Transformer or Unit Auxiliary Transformer (Backfeed Mode).

Amendment No. 42,-59,-51,-52 -191 -112,-144,-151,161 3/4.7-13 1

MMITING CONDITIONS FOR OPERATION SURVEII1ANCE REOUIREMENTS 3.7 CONTAINMENT SYSTEMS (Cont) 4.7 CONTAINMENT SYSTEMS (Cont)

B.

Standby Gas Treatment System and B.

Standby Cas Treatment System and Control Room Hirh Efficiency Air Control Room High Efficiency Air Filtration System (Cont)

Filtration System (Cont)

2. Control Room High Efficiency

2. Control Room High Efficiency 61E Filtration System Air Filtration System a Except as specified in

a. At least once per operating Specification 3.7.B.2.c or cycle the pressure drop l

3.7.B.2.e below, both trains across each combined filter of the Control Room High train shall be demonstrated Efficiency Air Filtration to be less than 6 inches of System used for the water at 1000 cfm or the processing of inlet air to calculated equivalent.

the control room under accident conditions and the

b. 1. The tests and analysis of diesel generator (s) required Specification 3.7.B.2.b for operation of each train shall be performed once of the system shall be per operating cycle or operable whenever secondary following painting, fire containment integrity is or chemical release in required and during fuel any ventilation zone handling operations.

communicating with the system while the system

b. 1. The results of the in-is operating.

place cold DOP tests on HEPA filters shall show

2. In-place cold DOP testing 2994 DOP removal.

The shall be performed after results of the each complete or partial halogenated hydrocarbon replacement of the HEPA tests on charcoal filter baq) or after any adsorber banks shall show structural maintenance on 2994 halogenated the system housing which hydrocarbon removal when could affect the HEPA test results are filter bank bypass extrapolated to the leakage.

initiation of the test.

3. Halogenated hydrocarbon

2. The results of the testing shall be laboratory carbon sample performed after each analysis shall show a95%

complete or partial methyl iodide removal at replacement of the a velocity within 10% of charcoal adsorber bank or system design, 0.05 to after any structural 0.15 mg/m8 inlet methyl maintenance on the system iodide concentration, housing which could 270% R.H., and h125 ' F.

affect the charcoal The analyris results are adsorber bank bypass to be verified as leakage.

acceptable within 31 days after sample removal, or

4. Each train shall be declare that train operated with the heaters inoperable and take the in automatic for at least 15 minutes every month.

Amendment No. 42 52,-1121-144 -151,161 3/4.7-14 1

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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 3.7 CONTAINMENT SYSTEMS (Cont) 4.7 CONTAINMENT SYSTEMS (Cont)

B.

Standby Gas Treatment System and B.

Standby Gas Treatment System and Control Room High Efficiency Air Control Room High Efficiency Air Filtration System (Cont)

Filtration System (Cont) actions specified in

5. The test and analysis of 3.7.B.2.c.

Specification 3.7.B.2.b.2 shall be performed after every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of system operation.

c From and after the date that one train of the Control

c. At least once per operating Room High Efficiency Air cycle demonstrate that the Filtration System is made or inlet heaters on each train found to be incapable of are operable and capable of supplying filtered air to an output of at least 14 kw.

the control room for any reason, reactor operation or refueling operations are permissible only during the succeeding 7 days providing that within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months all active components of the other CRHEAF train shall be demonstrated operable.

If the system is not made fully operable within 7 days, reactor shutdown shall be initiated and the reactor shall be in cold shutdown within the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months and irradiated fuel handling operations shall be terminated within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Fuel handling operations in progress may be completed.

d. Perform an instrument

d. Fans shall operate withini functional test on the 10% of 1000 cfm.

humidistats controlling the heaters once per operating

e. During refueling, one train cycle.

of the CRHEAF can be without its safety-related bus and/or emergency diesel generator without enterin5 the LCO action statement provided the following conditions are met:

- Fuel movement will not occur until five days following reactor shutdown.

Prior to and during fuel movement, the SB0 D/G or the Amendment No. 42 r 511-57 5 -112 r -144 -15L161 3/4.7-15 1

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' LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 3.7 CONTAINMENT SYSTEMS (Cont) 4.7 CONTAINMENT SYSTEMS (Cont)

Shutdown Transformer is required to be operable and capable of supply power to the emergency bus.

- Fuel movement will not occur until the reactor vessel is flood up to elevation 114'.

- The train of CRHEAF without is safety related bus or without its emergency diesel generator will have power supplied from a normal offsite source via a non safety-related bus.

The normal offsite source consists of either the Startup Transformer or Unit Auxiliary Transformer (Backfeed Mode).

C.

Secondary Containment C.

Secondary Containment

1. Secondary containment integrity

1. Secondary containment shall be maintained during all surveillance shall be performed modes of plant operation except as indicated below:

when all of the following conditions are met.

a. A preoperational secondary containment capability test

a. The reactor is suberitical shall be conducted after and Specification 3.3.A is isolating tim rasctor

- D' building and placing either standby gas treatment system

b. The reactor water filter train in operation.

temperature is below 212 *F Such tests shall demonstrate and the reactor coolant the capability to maintain system is vented.

1/4 inch of water vacuum under calm wind (<5 mph)

e. No activity is being conditions with a filter performed which can reduce train flow rate of not more the shutdown margin below than 4000 cfm.

that specified in I

Specification 3.3.A.

b. Additional tests shall be performed during the first

d. The fuel cask or irradiated operating cycle under an fuel is not being moved in adequate number of different i

the reactor building.

environmental wir.d conditions to enable valid

2. If Specification 3.7.C.1 cannot extrapolation d the test be met, procedures shall be results.

initiated to establish conditions listed in Speci-

c. Secondary containment fication 3.7.C.1.a through d.

capability to maintain 1/4 inch of water vacuun under Amendment No. 0,161 3/4.7-16

LIMITING CONDITIONS FOR OPEAATION SURVEILLANCE REQUIREMENTS

^

3 - 7.

CONTAINMENT SYSTEMS'(Cont) 4.7

-CONTAINMENT SYSTEMS (Cont)

C.

-Secondary Containment-(Cont)

C.

Secondary Containment (Cont) i e

calm wind (5 mph) conditions with a filter train flow rate of not more than 4000' l

cfa, shall be~ demonstrated l

at each refueling outage-prior to refueling.-

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l Amendment No. 0,161 3/4.7-17 i

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ML20081H894

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