ML20056B389

Amends 43 & 8 to Licenses NPF-39 & NPF-85,respectively, Revising Surveillance Requirements for Refueling Platform Main & Auxiliary Hoists to More Accurately Reflect Actual Use

ML20056B389
Person / Time
Site:	Limerick
Issue date:	08/16/1990
From:	Butler W Office of Nuclear Reactor Regulation
To:
Shared Package
ML20056B390	List: ML20056B389 ML20056B391
References
NUDOCS 9008280215
Download: ML20056B389 (16)

Text

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PHILADELPHIA ELECTRIC COMPANY 00CKET NO.~ 50-352 LIMERICK GENERATING STATION, UNIT 1 t

i AMENDMENT TO FACILITY OPERATING LICENSE f

Amendment No. 43-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 22, 1990, 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

.t Chapter I; B.

The facility will operate in conformity with the application, the-provisions of the Act, and the rules and regulations of the

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Commission; j

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; i

D.

The issuance of this amendment will not be inimical to the common j

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 i

of the Commission's regulations and all applicable requirements have-been satisfied.

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 Specificaticos contained in Appendix A and the Environmental Protect 4n Plan contained in Appendix B, as revised 1

through Amendment No. 43

, are hereby incorporated into this licease.

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

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.This license amendment'is effective as of its date of issuance.=

FOR THE NUCLEAR REGULATORY COMMISSION

. Original signed by-Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects - 1/II

'A'tachment:

t Changes.to-the Technical Specifications Date~of-Issuance: August 16,'1990 i

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This license amendment is effective as'of its date of issuance.

FOR THE NUCLEAR PEGULATORY COMMISS10t!

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Walter R. Butler, Director Project Directorate-I-2 Division of Reactor Projects - 1/II

Attachment:

Changes to the Technical Specifications-

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Date of-.If;uance:

August 16, 1990 i

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ATTACHMENT TO LICENSE AMENDMENT NO. 43 FACILITY OPERATING LICENSE NO. NPF-39 DOCKET NO. 50-352 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.

Overleaf pages are provided to maintain document completeness.*

Remove Insert 3/4 9-7 3/4-9-7*

3/4 9-8' 3/4 9-8 3/4 9-9 3/4 9-9 3/4 9-10 3/4 9-10*

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REFUELING OPERATIONS 3/4.9.5 COMMUNICATIONS LIMITING CONDITION FOR OPERATION 3.9.5 Direct communication shall be maintained between the control room and

. refueling floor personnel.

APPLICABILITY:

OPERATIONAL CONDITION 5, during CORE ALTERATIONS.*

ACTION:

When direct communication between the control room and refueling floor personnel cannot be maintained, immediately suspend CORE ALTERATIONS.*

i SURVEILLANCE REQUIREMENTS 4.9.5 Direct. communication between the control room and refueling floor personnel shall be demonstrated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> prio. to the start of and at

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least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during CORE ALTERATIONS.*

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• Except movement of incore instrumentation and control rods with their

' normal drive system.

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LIMERICK - UNIT 1 3/4 9-7 w

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3/4.9.6 REFUELING PLATFORM L

LIMITING CONDITION FOR OPERATION i

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3.9.6 The refueling platform shall be OPERABLE and used for handling fuel assemblies or control rods within the reactor pressure-vessel.

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APPLICABILITY:

During handling of fuel assemblies or control rods within the reactor pressure vessel, q

l ACTION:

With the requirements for refueling platform OPERABILITY not satisfied, suspend use of any inoperable ' refueling platform equipment from operations involving the handling of control rods and fuel assemblies within the reactor pressure I

vessel after placing the load in a safe condition.

1 SURVEILLANCE REQUIREMENTS 4.9.6.1 The refueling platform main hoist used for handling of fuel assemblies within the reactor pressure vessel shall be demonstrated OPERABLE within 7 days 1

prior -to.the start of. such operations by:

a.

Demonstrating operation of the-overload cutoff on the main hoist when the load exceeds 1150 1 50 pounds.

b.

Demonstrating operation of the. hoist: loaded control rod block interlock onlthe main hoist when the load exceeds 485 t 50 pounds.

c.

Demonstrating operation of the redundant loaded interlock on the main

~ hoist when the load exceeds 550 + 0, - 115 pounds,

d. _

Demonstrating operation of the uptravel interlock when uptravel brings the top of the active-fuel to not less than 8 feet 0 inches below the l

normal water level.

o LIMERICK - UNIT 1 3/4 9-8 Amendment No. 43

REFUELING OPERATIONS SURVEILLANCE REQUIREMENTS (Continued) 4.9.6.2. The refueling platform frame-mounted auxiliary hoist used for handling of control rods within the reactor pressure vessel shall be demon-strated OPERABLE within 7 days prior to the use of such equipment by:

a.

Demonstrating operation of the overload cutoff on the frame mounted hoist when the load exceeds 500 1 50 pounds.

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b.

Demonstrating operation of the uptra. vel mechanical stop on tne frame ^

'l mounted hoist when uptravel brings the top of a control rod to not less than 6 feet 6 inches below the normal-fuel storage pool water i

r level.

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4.9.6.3' The refueling platform monorail mounted auxiliary hoist used for handling of control rods within the reactor pressure vessel sh.11 be demonstra--

-ted OPERABLE within 7 days prior to the use of such equipment by:

a.

Demonstrating operation of the overload cutoff on the monorail hoist when the load exceeds 500 1 50 pouris.

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b.

Demonstrating operation of the uptravel mechanical,stop on the monorail hoist when uptravel brings the top of a control rod to not less than 6 feet 6 inches below the normal fuel storage pool water level.

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LIMERICK - UNIT 1 3/4 9-9 Amendment No, 43 L"

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'i REFUELING OPERATIONS-3/4.9.7~ CRANE TRAVEL-SPENT FUEL STORAGE POOL LIMITING CONDITION FOR OPERATION

3. 9. 7 - Loads in excess'of 1200' pounds shall be prohibited from travel over fuel assemblies in the spent fuel storage pool-racks.

APPLICABILITY:

With_ fuel assemblies in the spent fuel storage pool' racks.

ACTION:

I With the requirements of the above specification not satisfied, place the crane load in a safe condition..The provisions of Specification 3.0.3 are not applicable.

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l SURVEILLANCE REQUIREMENTS j

4,9.7 Crane interlocks which prevent crane travel over fuel assemblies in

.the spent fuel-storage pool. racks shall.be demonstrated OPERABLE within 7 days i

prior to and at least once per 7 days.during crane operation.

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LIMERICK - UNIT 1 3/4 9-10

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NUCLEAR REGULATORY COMMISSION.

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i PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-353 LIMERICK GENERATING STATION, UNIT 2 t

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

8 License No. NPF-85 1.

The Nuclear Regulatory Commission (the Commission) has found that-A.

The application for amendment by Philadelphia Electric Company (the licensee) dated June 22, 1990, 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; 8.

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

.i Commission; C.

T.cre 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 common defense and_ security or to the. health and safety of the public; and l:

E.

The issuance of this amendment is in accordance with 10 CFR Part 51 L

of the Commission's regulations and all applicable requirements have l

been satisfied.

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2.

Accordingly, the license is amended by changes to the Technical Specifications l-as indicated in.the attachment to this license amendment, and paragraph 2.C.(2)-

L of Facility Operating License No. NPF-85 is hereby amended to read as follows:

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

8 are hereby incorporated into this license.

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

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This license: amendment is effective as of-its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Original signed by-Walter R. Butler, Director Project Directorate 1-2.

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Division of Reactor Projects - 1/11

/sttachment:

Charges to the Technical h ; Specifications

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Date oflltsuance:

August 16, 1990

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This license amendment is effective as of its date of' issuance.

FORTHENUCLEARREGULATdRY-COMMISSIONi f/

'L Walter.R. Butler, Director'

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Project Directorate I '

Division of Reactor Projects - I/II

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Attachment:

j Changes to the Technical j

Specifications

.!.i Date of Issuance: August 16, 1990 I

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'l ATTACHMEKr TO LICENSE AMENDMENT'NO. 8 FACILITY OPERATING LICENSE NO. NPF-85 DOCKET NO. 50-353

~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' area of change.

Overleaf pages are; provided tu maintain document completeness.*

Remove Insert 3/4 9-7 3/4 7*

3/4 9-8 3/4 9-8 m

3/4 9 3/4 '9-9 z

3/4 9-10 3/4 9-10*

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g REFUELING OPERATIONS 3/4.9.5 COMMUNICATIONS

, LIMITING CONDITION FOR OPERATION 3.9.5 Direct communication shall be maintained between the control room and refueling floor personnel.

APPLICABILITY:

OPERATIONAL CONDITION 5, during CORE ALTERATIONS.*

ACTION:-

When direct communication between the control room and refueling floor-personnel cannot be maintained, immediately suspend CORE ALTERATIONS.*

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SURVEILLANCE REQUIREMENTS 1

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- 4.9.5 ~ Direct communication between the control room and refueling floor l

D personnel,shall be demonstrated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> prior to the start of and at

'aast once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during CORE ALTERATIONS.*

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• Except movement of incore instrumentation and control rods with their normal drive system.

LIMERICK - UNIT 2 3/4 9-7

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REFUELING OPERATIONS' 3/4i9.6 REFUELING PLATFORM i

LIMITING CONDITION FOR OPERATIO'N 3,9.6 The refueling platform shall be OPERABLE and used for handling fuel assemblies or control rods within the reactor pressure vessel.

APPLICABILITY:

During handling of fuel assemblies or control rods within the reactor pressure vessel.

ACTION:

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With the requirements.for refueling platform OPERABILITY not satisfied, suspend use of any' inoperable refueling platform equipment from operations involving the handling of' control rods and fuel assemblies within the reactor pressure vessel after placing the load in a safe condition.

SURVEILLANCE REQUIREMENTS 4.9.6.1 'The refueling platform main hoist used for handling of fuel assemblies within the reactor pressure vessel shall be demonstrated OPERABLE within 7 days prior to the start of such operations by:

a, Demonstrating operation of the overload cutoff on the main hoist when the load exceeds 1150 1 50 pounds.

b.

Demonstrating operation of the hoist loaded control rod block. interlock on the main hoist when the load exceeds 485 1 50 pounds.

c.

- Demonstrating operation 'of the redundant loaded interlock on the main hoist when the. load exceeds 550 + 0, - 115 pounds.

l d.

Demonstrating operation of the uptravel interlock when uptravel brings I

the top of the active fuel to not less.than 8 feet 0 inches below the l

normal water level.

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LIMERICK - UNIT 2 3/4 9-8 Amendment No. 8 l

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REFUELING OPERATIONS

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o SURVEILLANCE REQUIREMENTS (Continued) a 4.9.6.2 The refueling platform frame-mounted auxiliary hoist used for handling of control rods within the reactor pressure vessel shall be demon-

.strated OPERABLE within 7 days-prior to.the. use of such equipment by:

a.

Demonstrating operation of the overload cutoff on the frame mounted hoist when the load exceeds 500 1 50 pounds.

b.

Demonstrating operation of the uptravel mechanical stop on the frame mounted hoist when uptravel brings the top of a control rod to not less than 6 feet 6 ir.ches below the normal fuel. storage pool water level.

l 4.9.6.3 The refueling platform monorail mounted auxiliary hoist used-for handling of control rods within the reactor pressure vessel shall be demonstra-ted OPERABLE within 7 days prior to the use of such equipment by:

a.

Demonstrating operation of the overload cutoff on the monorail hoist when the load exceeds 500 1 50 pounds, b.

Demonstrating operation of the uptravel mechanical stop on the monorail hoist when uptravel brings the top of a control rod'to not less than 6 feet 6 inches below the normal fuel storage pool water level.

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i LIMERICK - UNIT 2 3/4 9 Amendment No. 8

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'LREFUELING OPERATIONS I

'3/4.9.7 CRANE TRAVEL-SPENT FUEL' STORAGE POOL LIMITING CONDITION FOR OPERATION

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3.9.7-l Loads in excess of 1200 pounds shall be prohibited from travel over fuel assemblies'in the spent fuel storage pool racks.-

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. APPLICABILITY:. With fuel assemblies in the spent fuel storage pool racks.

ACTION:

With-theLrequirements-of the above specification not satisfied, place the crane load-in aLsafe condition.. The provisions of Specification 3.0.3 are not

.appli cabl e'.

SURVEILLA'CE REQUIREMENTS N

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6.9.7 Crane interlocks which prevent crane travel over fuel' assemblies in

'he spent. fuel storage pool racks shall be demonstrated OPERABLE within 7 ciays-prior, to' and at<gleast once per 7 days during crane operation.

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l LLIMERICK' UNIT 2 3/4 9-10

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