Text

Amend 58 to License NPF-39,providing one-time Extension in AOT for RHR Svc Water Sys & Suppression Pool Cooling Mode of RHR Sys.Rev Extends AOT from 72 H to 168 H During Second Refueling Outage
	ML20127E408
Person / Time
Site:	Limerick
Issue date:	01/11/1993
From:	Rinaldi F; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20127E412	List: ML20127E408; ML20127E416;
References
	NUDOCS 9301190287
	Download: ML20127E408 (7)
	v • d • e

- - - _ _ _ _ _

p" " G W l

3' UNITED STATES c,

,i NUCLEAR REGULATORY COMMISSION W ASHINoTON, D C. 20U4 o

%.... /

PHilADELPALA ELECTRIC COMPANY DOCKET NO. 50-352 LIMERICK GENERATING STATION. UNIT 1 AMENDMENT TO FACILITY OPFRATING LICENSI, Amendment No. 58 License No. HPF-39 1.

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

A.

The application for amendment by Philadelphia Electric Company (the licensee) dated November 6, 1992, complies with the standards and recuirements of the Atomic Energy Act of 1954, as amended (the Act),

anc 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 tha comon defense and security or to the health and safety of the pub 1_ic; 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.

@@l1 $$$ So a'

l

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)llows:of Facility Operating License No. NPF-39 is hereby amended to read as fo Technical Snecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 58 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.

FOR THE NUCLEAR REGULATORY COMMISSION CYP Y &

3 Charles L. Miller, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: January 11, 1993 i

em.-

,_-,w-,

s.

w

1 ATTACHMENT-TO LICENSE AMEN 0 MENT NO.58 FACILITY OPERATING LICENSE N0. NPF-39 DOCKET NO. 50- M1 Replace the following pages of the Appendix A Technical Specifications with the attached pages.

The revised pages are identified by Amendment number and i

contain vertical lines indicating the area of change. Overleaf pages are provided to maintain document completeness.*

fltm.1Y.9 101Rr_t 3/4 6-15 3/4 6-15' 3/4 6-16 3/4 6-16 3/4 7-1 3/4 7-1 3/4 7-2 3/4 7-2*

4 I

A f

t' 6

f e

e t

F m.

e._ _ _,_ _ _ ________=_ _ _

m m-

.... - -..,, - -, ~.-.i. J

p CONTAINMENT $YSTEMS l

SUPD4ES$'CN POOL $ PRAY t!":~N CON 0! TION FOR OPERATION 3.6.2.2

'he suppression pool spray mode of the residual heat removal (RHR) 5,nen snill ee OPERABLE with two independent loops, each loop consisting of:

1 a.

One OPERABLE RHR pump, and An OPERABLE flow path capable of recirculating water from the D.

suppression chamber through an RHR heat exchanger and the suppression pool spray sparger(s).

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

With one suppression pool spray loop inoperable, restore the inoperable a.

loop to OPERABLE status within 7 days or be in at least HOT $HUTDOW within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOW within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b.

With both suppression pool spray loops inoperable, restore at least one loop to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or be in at least HOT SHUTOOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWa within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

I SURVEILLANCE REQUIREMENTS 4.6.2.2 The suppression pool spray mode of the RHR system shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

b.

By verifying that each of the required RNA pumps develops a flow of

. at least 500 gpa on recirculation flow through the RHR heat exchanger and the suppression pool spray sparger when tested pursuant to Speci-l fication 4.0.5.

Whenever both RHR subsystems are inoperable, if unable to attain COLD SHUTDOWN as required by this ACTION, maintain reactor coolant temperature as low as practical by use of alternate heat removal methods.

q LIMERICK-- UNIT 1 3/4 6-15

~

i CONTAINMENT SYSTEMS SUPPRESS 10N POOL COOLING LlHITING CONDITION FOR OPERATION 3.6.2.3 The suppression pool cooling mode of the residual heat removal (RHR) system shall be OPERABLE with two independent loops, each loop consisting oft a.

One OPERABLE RHR pump, and b.

An OPERABLE flow path capable of recirculating water from the suppression chamber through an RHR heat exchanger.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

With one suppression pool cooling loop inoperable, restore the inoperable a.

loop to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 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 .#

l b.

With both suppression pool cooling loops inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN

within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS ___

4.6.2.3 The suppression pool cooling mode of the RHR system shat) be demonstrated OPERABLE:

At least once per 31 days by verifying that each valve (manual, power-a.

operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

b.

By verifying that each of the required RHR pumps develops a flow of at least 10,000 gpm on recirculation flow through the flow path including the RHR heat exchanger and its associated _ closed bypass valve, the suppression pool and the full flow test line when tested pursuant to a

Specification 4.0.5.

Whenever both RHR subsystems are inoperable, if unable to attain COLD SHUTDOWN low as as required by this ACTION, maintain reactor coolant tempercture as practical by use of alternate heat removal methods.

The Allowed Outage Time (A0T) of the 'B' Loop of the Suppression Pool Cooling (SPC).

mode of the RHR System may be extended up to 168 hours0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months (7 days) to allow repair of HV-51-1F0688 and HV-51-2f068B during the Unit 2 second refueling outage (2R02).

LIMERICK - UNIT 1 3/4 6-16 Am m! ment No. 37, 58

3/4.7 PLANT SYSTEMS F771 SERVICE WATER SYSTEMS RESIDUAL HEAT REMOVAL SERVICE WATER SYSTEM - COMMON SYSTEM LIMITING CONQlTION_FOR OPERATION 3.7.1.1 At least the following independent residual heat removal service water (RHRSW) system subsystems, with each subsystem comprised of:

a.

Two OPERABLE RHRSW pumps, and b.

An OPERABLE flow path capable of taking suction from the RHR service water pumps wet pits which are supplied from the spray pond or the cooling tower basin and transferring the water through one Unit 1 RHR heat exchanger.

hall be OPERABLE:

l a.

In OPERABLE CONDITIONS 1, 2, and 3, two subsystems, b.

In OPERABLE CONDITIONS 4 and 5, the subsystem (s) associated with systems and components required OPERABLE by Specification 3.4.9.2, 3.9.11.1, and 3.9.11.2.

APPLICABillTY:

OPERATIONAL CONDITIONS 1, 2, 3, 4, and 5.

ACTION:

a.

In OPERATIONAL CONDITION 1, 2, or 3:

1.

With one RHRSW pump inoperable, restore the inoperable pump to OPERABLE status within 30 days, 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 .

2.

With one RHRSW pump in each subsystem inoperable, restore at least one of the inoperable RHRSW pumps to OPERABLE status within 7 days 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 .

3.

With one RHRSW subsystem otherwise inoperable, restore the inoperable subsystem to OPERABLE status with at least one OPERABLE RHRSW pump within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 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 .l l

4.

With both RHRSW subsystems otherwise inoperable, restore at least one subsystem to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or be in at least HOT SHUTOOWN 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 .

Whenever both RHRSW subsystems are inoperable, if unable to attain COLD SHUT 00WN as required by the ACTION, maintain reactor coolant temperature as low as practical by use of alternate heat removal methods, i The Allowed Outage Time (A0T) of the 'B' RHR$W Loop may be extended up to 168 hours0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months (7 days) to allow repair of HV-51-1F0688 and HV-51-2F0688 during the Unit 2 second refueling outage (2R02).

LIHERICK - UNIT 1 3/4 7-1 Amendment No. 58

PLANT SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

ACTION:

(Continueo) 5.

With two RHR$W pump / diesel generator pairs

inoperable, restore at least one inoperable RHRSW pump / diesel generator patr* to OPERA 8LE status within 30 days, or be in at least HOT SHUTDOWN within 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 . The provisions of specification 3.0.4 are not applicable.

6.

With three RHR$W pump / diesel generator pairs

fnoperable.

restore at least one inoperable RHR$W pump / diesel generator pair

to OPERA 8LE status within 7 days, or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTOOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

7, With four RHR$W pump / diesel generator pairs

inoperable, restore at least one inoperable RHRSW pump / diesel generator patr* to OPERA 8LE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-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 , b.

In OPERATIONAL CON 0! TION 3 or 4 with the RHR$W subsystee(s) which is associatedwithanRHRlooprequiredOPERABLEbySpecificatIon 3.4.9.1 or 3.4.9.2, inoperable, declare the associated RHR loop inoperable and take the ACTION required by Specification 3.4.9.1 or 3.4.9.2, as applicable, c.

In OPERATIONAL CONDITION 5 with the RHR$W subsystem (s), which is associated with an RHR loop required OPERA 8LE by Specification 3.9.11.1 or 3.9.11.2, inoperable, declare the associated RHR system inoperable and take the ACTION required by Specification 3.9.11.1 or 3.9.11.2, as applicable.

SURVEILLANCE REQUIREMENTS 4.7.1.1 At least the above required residual heat removal service water system subsystee(s) shall be demonstrated OPERA 8LE:

a.

At least once per 31 days by verifying that each valve in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

"A RHR$W pump / diesel generator pair consists of a RHRSW pump and its associated diesel generator.

If. either a RHRSW pump or its' associated diesel generator becomes inoperable, then the RHRSW pump / diesel generator pair is inoperable.

l:

LIMERICK - UNIT 1 3/4 7-2 Amendment No. 27, 40 l

MAY 3 01990 4

(Ms 4*

g ed

,A

(*

h

--

ML20127E408

Text

Attachment:

Navigation menu

Search