ML20071C568

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Amend 87 to Licenses DPR-44 & DPR-56,changing Tech Specs Re Surveillance Requirements to Permit Alternate Method for Performing Core Spray Loop Flow Rate Test
ML20071C568
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 02/18/1983
From: Stolz J
Office of Nuclear Reactor Regulation
To:
Philadelphia Electric Co, Public Service Electric & Gas Co, Delmarva Power & Light Co, Atlantic City Electric Co
Shared Package
ML20071C569 List:
References
DPR-44-A-087, DPR-56-A-087 NUDOCS 8303020423
Download: ML20071C568 (10)


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PHILADELPHI ELECTRIC COWANY PUBLIC SERVICE ELECTRIC AND GAS Co@ANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 l

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AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 87 License No. DPR-44 l.

1.

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

i A.

The application for amendment by Philadelphia Electric Company, et l

al. (the licensee) dated December 1,1982, complies with the

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standards and requirements of the Atomic Energy Act of 1954, l

as amended (the Act), and the Commission's rules and regulations l

set forth in 10 CFR Chapter I;

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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 (1) 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 C,ommission'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 i

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 changes to i;he Technical Spec-ifications as' indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No.'.DPR-44 is

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hereby amended to read as follows:

Technical Specifications The Technical Specifications contained in Appendices A and B, as reviped through Amendment No. 87, ar,e.hereby incorporated in the license.

PECO shall operate the fac_ijjty in accordance

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with the Technical Specifications.

l 8303020423 830218 PDR ADOCK 05000277 j

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PDR i

2-3.

This license amendment is effective as of the data of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION in F. Stolz, Chief perating Reactors Branch #4 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: February 13, 1983 e

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ATTACHMENT TO LICENSE AMENDMENT NO. 87 FACILITY OPERATING LICENSE NO. DPR-44 DOCKET NO. 50-277 Replace the following page and add the new page of the Appendix "A" Technical Specifications with the enclosed pages. The pages are identified by Amendment number and contain a vertical line indicating the area of change.

Remove Insert 125 125 125a O

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' LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5.A Core Spray &

4.5.'A Core Spray &

LPCI Subsystem (cont'd)..,,

LPCI Subsystem (cont'd)

Both CSS shall be operable Item Frequency whenever irradiated fuel is in the vessel and prior (d)

Pump Flow Rate Once/3 months to reactor startup from a

  • EachPumpineachlbopshall Cold Shutdown condition except as specified in deliver at least 3125 gym 3.5.A.2 and 3.5.F.3 below:

against a system head corres-ponding to a reactor vessel pressure of 105 psig.

(e)

Core Spray Header AP Instrumentation Check Once/ day

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i Calibrate

.Once/3 months (f)

Operability In accordance check to ensure with 4. 5. A.2, that pumps will 4.5.A.4 and start and motor 4.5.A.5.

operated inject-ion valves will open.

2. From and after the date
2. When~ it is determined that one that one of the core core spray subsystem is inoper-spray subsystems is able, the operable core spray made or found to be subsystem and the LPCI subsys-inoperable for any reas-tems shall be demonstrated on, continued reactor to be operable in accordance operation is permiss-with 4.5.A.l(f) and 4.5. A.3 (e) ible only during the within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and at least succeeding seven days once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> thereafter provided that during until the inoperable core l

such seven days all spray subsystem is restored l

active components of to operable status.

l the other core spray subsystem and active

3. LPCI Subsystem Testing shall i

l components of the LPCI be as follows:

subsystem are operable.

  • Until the required

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modification is completed, the loop flow rate test at 6250 gpm against a system head corresponding to a reactor vessel pressure of 105 psig will be performed l

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to satisfy surveillance requirements.

- -125-l Amendment No. 25' J7, pg, 87

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PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS Item Frequency (a) Simulated Automatic Once/ operating Actuation Test Cycle (b) Pump operability Once/l month

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-125a-Amendnjent No. 87 nee i

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UNITED states'

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.I wassmarom.o.c.zeses PHILADELPHik'tLECTRICCOWANY P_UBLIC SERVICE ELECTRIC AND GAS CO W ANY DELMARVA POWER AND LIGHT COMPANY ATLANTlC CITY ELECTRIC COMPANY DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 87 License No. DPR-56 1.

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

A.

The application for amendment by Philadelphia Electric Company, et al. (the licensee) daced December 1,1982, 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'fortn :s 10 CFR Chapter I; B.

The facility will operate in confomity with the application, i

the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (11) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment wi1Pnot be inimical to the common defense and security or to the heatth and safety of the public; and E.

The issuance of thisIamendment is in - cordance with 10 CFR Part 51 of the Commission's regulatio-

. l applicable requirements have been satisfied.

2.

Accordingly, the license is amended t_

...ges to the Technical Spec-ifications as indicated in the attachment to this l'icense amendment and paragraph 2.C.'(2)' of facility Operating License No. 'DPR-56 is hereby amended to read as follows:

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 87, are hereby incorpcrated in the licepsc. P with the Technical.ECO shall operate th.e facility in accordance Specifications.

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3.

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

FOR THE NUCLEAR REGULATORY COMMISSION ohp F. Stolz, Chief 0

ating Reactors Branch #4 ision of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: February 18, 1983 l' t M

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ATTACHMENT Th EICENSE AMENDMENT NO. 87 FACILITY OPERATING LICENSE NO. DPR-56

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DOCKET NO. 50-278 Replace the following page and add the new page of the Appendix "A" Technical Specifications with the enclosed pages. The pages are identified by Amendment number and contain a vertical line indicating the area of change.

Remove Insert

-125 125 125a e

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i PBAPS

' LIM'ITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5.A Core Spray &

t.5.A Core Spray &

LPCI Subsystem (cont'd) ' %

LPCI Subsystem (cont'd)

Both CSS shall be operable Item Frequency whenever irradiated fuel is in the vessel and prior (d)

Pump Flow Rate Once/3 months to reactor startup from a Cold Shutdown condition

  • Each Pump in each loop shall except as specified in deliver at least 3125 gpm 3.5.A.2 and 3.5.F.3 below:

against a system head corres-ponding to a reactor vessel pressure of 105 psig.

(e)

Core Spray Header AP Instrumentation Check Once/ day Calibrate-Once/3 months

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(f)

Operability In accordance check to ensure with 4.5.A.2, that pumps will 4.5.A.4 and start and motot 4.5.A.5.

operated inject-ion valves will open.

2. From and after the date
2. When'it is determined that one that one of the core core spray subsystem is inoper-spray subsystems is able, the operable core spray made or found to be subsystem and the LPCI subsys-

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inoperable for any reas-tems shall be demonstrated

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on, continued reactor to be operable in accordance operation is permiss-with 4.5.A.1(f) and 4.5.A.3 (e) ible only during the within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and at least succeeding seven days once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> thereafter provided that during until the inoperable core such seven days all spray subsystem is restored active components of to operable status.

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the other core spray subsystem and active

3. LPCI Subsystem Testing shall components of the LPCI be as follows:

subsystem are operable.

  • Until the required modification is completed, the loop flow rate test at 6250 gpm against a system head corresponding to a reactor vessel pressure of 105 psig will be performed

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to satisfy surveillance requirements.

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-125-Amendment tio. 27,. 97, 87 5

r une,a LIMITING CONDITIONS IOR OPERATION SURVEILLANCE REQUIREMENTS Item.

Frequency

- (a) Simulated Automatic Once/ operating Actuation Test Cycle (b) Pump operability Once/l month 4

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-125a-l-

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Amendment No. 87 O

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