Text

Amends 59 & 24 to Licenses NPF-39 & NPF-85,respectively. Amends Provide one-time Rev of TS Surveillance Requirements for Standby Liquid Control Sys
	ML20128E508
Person / Time
Site:	Limerick
Issue date:	01/29/1993
From:	Chris Miller; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20128E511	List: ML20128E508; ML20128E515;
References
	NUDOCS 9302100489
	Download: ML20128E508 (10)
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'n UNITED STATES 3

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,i NUCLEAR RECULATORY COMMISSION o

WASHINoToN, D C. 206f4 PHILADELPHIA 1110.IRIC COMPANY DOCKET N0. 52-1H UMLQCK GENERATING ST611@kUNIT 1 AMENDMf17.19 FAClllTY,QPERAilNG.ll[l[M Amendment No.59 License No. NPF-39 1.

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

A.

Tiie application for amendment hy Philadelphia Electric Company (the licensee) dated April 3,1992, as supplemented January 21 and 22, 1993, 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 roles and regulations of the Commission; L.

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; 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.

2.

Accordingly, the license is a:nended by changes to the Technical Specifications as indicated in the attachnient to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-39 is hereby amended to read as follows:

9302100409 930g29 DR ADOCK 05000352 PDR

2-i Technical Scecifications the Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B,-as revised through Amendment i

No. 59 are hereby incorporated into this-license.

Philadelphia Electric Company shall operate the f acility 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 Ytt hlA u

p Charles L. Miller, Director Project Directorate 1-2 i

Division of Reactor Prcjects - I/11 l

Office of Nuclur Reactor Regulation

Attachment:

I Changes to the Technical Specifications Date of Issuance: January 29, 1993

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t ATTACHMENT TO LICENSE AMENDMENT NO. 59 i

FACILITY OPERATING LICENSE NO. NPF-3.2 DOCKET NO. 50-352 l.r 1

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.

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REACVIVITY CONTROL SYSTEMS 3/4.1.5 STANDBY LIQUID CONTROL SYSTEM LIMITING C0HDITION FOR OPERATION 3.1.5 The standby liquid control system, consisting of a minimum of two pumps and corresponding flow paths, shall be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 5*

ACTION:

e, in OPERATIONAL CONDITION 1 or 2:

1.

Mth only one pump and corresponding explosive valve OPERABLE, restore one inoperable pump and correspending explosive valve to OPERABLE status within 7 days or be in at least HOT SHUT 00WN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

2.

With the standby liquid control system otherwise inoperable, restore the system 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 SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , b.

In OPERATIONAL CONDITION 5*:

1.

With only one pump and corresponding explosive valve OPERABLE, restore one inoperable pump and corresponding explosive valve to OPERABLE status within 30 days or insert all insertable control rods within the next hour.

2.

With the standby liquid control system otherwise inoperable, insert all insertable control rods within I hour.

SURVEILLANCE REQUIREMENTS 4.1.6 The standby liquid control system shall be demonstrated OPfRABLE:

a.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying that:

1 1.

The temperature of the sodium pentaborate solution is within the l

limits of Figure 3.1.5-1, 2.

The available volume of sodium penteborate solution is at least 4537 l

gallons.

1 3.

The tgmperature of the pump suction piping is greater than or equal to 10 F.

I With any control rod withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

LIMERICK - UNIT'1 3/4 1-19 Amendment No. 59.-

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SURVEILLANCE RfQUIREMENTS (Continued) b.

At least once per 31 days by:

1.

Verifying the continuity of the explosive charge.

2.

Determining by chemical analysis and calculation

that the available weight of sodium pentaborate is greater than or equal to 5389 lbs; the concentration of sodium pentaborate in solution is less than or equal to 13.8% and within the limits of Figure 3.1.5-1 and; the following e Jation is satisfied:

C x

Q

> 1

~

D % wt.

86 gpm where C = Sodium pentaborate soiution (% by weight)

Q = Two pump flowrate, as determined per surveillance requirement 4.1.5.c.

3.

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.

c.

Demonstrating that, when tested pursuant to Specification 4.0.5, the minimum flow requirement of 41.2 gpm per pump at a pressure of greater than y equal to 1190 psig is met, d.

At least once per 18 months during shutdown by:

1.

Initiating at least one of the standby liquid control system loops, including an explosive valve, and verifying that a flow path from the pumps to the reactor pressure vessel is available by pumping demineralized water into the reactor vessel. The replacement charge for the explosive valve shall be from the same manufactured b/ ch as the one fired or from another batch which has been certified oy having one of that batch successfully fired. All injection loops shall be tested in 3 operating cycles.

2.

- Demonstrating that all suction piping is unblocked by pumping from the storage tank through each discharge line, and pumping from the test tank back to the test tank through each loop.

3.

Demonstrating that 'A' storage tank heater is 00ERABLF.*** by verifying expected temperature rise of the sodium pentaborate solution in the storage tank af ter the heater is energized.

This test shall also be performed anytime water or boron is added to the 0

solution or when the solution temperature drops below 70 F.

shall also be performed whenever suction piping temperature drops J

- ThistesgF.

below 70

- - With tank heater ' A' inoperable, verify storage tank temperature is greater than 70 F every eight (B) hours.

l.IMERICK - UNIT 1 3/4 1-20 Amndment No. 59

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NUCLEAR REGULATORY COMMISSION 3

WASHINoTON, D.C.0556 e

r PHILADELPHLA ELECTRIC COMPANY 00CKET NO. 50-352 LIMERICK GENERATING STATION. UNIT 2

!LMENDMENT TO FACillTY OPERATING LICENSE Amendment No.24 License No. HPT-55 1.

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

A.

The application for amendment by Philadelphia Electric Company (thn licensee) dated April 3, 1992, as supplemented January 21 and 22, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

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

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

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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 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.

2.

Accordingly, the license is amended by cha.nges 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 L

amended to read as follows:

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Jachnical Specifications The Technical Specifications contained in Appendix A and the-Environmental Protection Plan contained in Appendix B, as revised through Amendment tio. 24

, 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 fiUCLEAR REGULATORY COMMISS10f1 UG a

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Charles L. Miller, Director Project Directorate 1-2 Division of Reactor Projects - 1/11 Office of 11uclear Reactor Regulation

Attachment:

Changes to 'he Technical Specifications Date of Issuance: January 29, 1993 1

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ATTACHMENT TO LICEllSE AMENDMENT t!Q. ?h__.

FAC1L1Tt 0ERATING l1[Lilli_1(QJP.L_RS QQCKET NO. 50-353 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.

ILenny_e h a r_t 3/4 1-19 3/4 1-19

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3/4 1-20 3/4 1-20

rtassiesit LOHikot hisRMs 3/4.1.5 STANDBY L! QUID CONVROL SYSTEM LIMITING CONDITION FOR OPERATION 3.1.5 The standby liquid control system, consisting of a minimum of two pumps and corresponding flow patts, shall be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 5*

ACTION:

a.

In OPERATIONAL. CON 0! TION 1 or 2:

1.

With only one pump and corresponding explosive valve OPERAULE, restore one inoperable pump and corresponding explosive valve to OPERABLE status within 7 days or be in at least HOT SHUT 00VN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

2.

With the ';tandby liquid control system otherwise inoperable, restore the system to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months r 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 , i

b.

In OPERATIONAL CONDITION 5*:

1.

With only one pump and corresponding explosive valve OPERABLE, restore one inoperable pump and corresponding explosive valve to OPERABLE status within 30 dayr. or insert all insertable control rods within the next hour.

2.

With the standby liquid control system otherwise inoperab4e, insert all insertable control rods within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

SURVEILLANCE REQUIREMENTS 4.1.5 The standby liquid control system shall be demonstrated OPERABLE:

a.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying that:

1.

The temperature of the sodium pentaborate solution is within the limits of Figure 31 1.5-1.

2.

The available volume of sodium pentaborate solution is at least 4537 gallons.

3.

Thetgmperatureofthepumpsuctionpipingisgreaterthanorequal to 10 F.

Miith any control rod withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

LIMERICK - UNIT 2 3/4 1-19 Amendment No.24

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SURVE!LLANCE REQUIREMENTS (Continued) b.

At least once per 31 days by:

l.

Verifying the continuity of the explosive charge.

2.

Determining by chemical analysis and calculation

that the available weight of sodium pentaborate is greater than or equal to 5389 lbs; the concentration of sodium pentaborate in solution is less than or equal to 13.8% and within the limits of Figure 3.1.5-1 and; the following equation is satisfied:

C x

0

> 1

~

13% wt.

86 gpm where C=Sodiumpentaboratosolution(%byweight)

Q = fwo pump flowrate, as determined per surveillance requirement 4.1.5.c.

3.

Verifying thnt 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.

c.

01monstrating that > when tested pursuant to Specification 4.0.5, the minimum flow requirement of 41.2 gpm per pump at a pressure of greater than or equal to 1190 psig is met, d.

At least once per 18 months during shutdown by:

1.

Initiating at least one of the standby liquid control system loops, including an explosive valve, and verifying that a flow path from the pumps to the reactor pressure vessel is availabic by pumping demineralized water-into the reactor vessel. The replacement charge for the explosive valve shall be from the same manufactured batch as the one fired or from another batch which has been certified by having one of that batch successfully fired. All injection loops shall be tested in 3 operating cycles, 2.

- Demonstrating that all suction piping is unblocked by pumping from the storage tank throigh each discharge line, and pumping from the test tank back-to the test tank through each loop.

3.

Demonstrating that 'A storage tank heater is OPERABLC*** by verifying agected temperature rise of the sodium pentaborate solution in the storage tank after the heater is energized.-

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This test shall also be performed anytime water or boron 15 added to the solution or when the solution temperature drops below 70,f..

- Thistesgshallalsobeperformedwheneversuctionpipingtemperaturedrops below 70 F.

- - With tank heater 'A' inoperable, verify storage tank temperature is greater 0

than 70 F every eight (8) hours.

LINERICK - UNIT 2-3/4 1-20 k.erriment No. 24

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ML20128E508

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