ML20244A425

Forwards Model Tech Specs for Use in Preparation of Proposed License Amend to Ensure Operability of Overpressure Protection Sys by Disabling Charging Pumps or Other Equipment.Proposal Requested within 45 Days

ML20244A425
Person / Time
Site:	San Onofre
Issue date:	08/28/1978
From:	Ziemann D Office of Nuclear Reactor Regulation
To:	James Drake SOUTHERN CALIFORNIA EDISON CO.
References
TAC-06836, TAC-6836, NUDOCS 7809070181
Download: ML20244A425 (10)

Text

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,- ," g # % UNITED STATES NUCl. EAR REGULATORY COMMISSION y $ WASHINGTON, D. C. 20555 g j

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August 28, 1978 Docket No. 50-206

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Southern California Edison Company ATTN: Mr. James H. Drake _.

.' Vice President 2244 Walnut Grove Avenue

. Post Office Box 800 Rosemead, California 91770 Gentlemen:

RE: OVERPRESSURE PROTECTION TECHNICAL SPECIFICATIONS In our earlier discussions with you regarding your overpressure protection system, we indicated that Technical Specifications would be necessary to ensure the operability of the system and to require the disabling of any equipment, such as charging pumps or safety injection pumps. Such specifications will ensure that the Appendix G limits for your reactor vessel will not be exceeded in the event of a pressure transient, assuming a single failure.

The enclosed model Technical Specifications are being provided for your guidance in preparation of your submittal for th'e San Onofre facility.

You are requested to submit your proposed Technical Specifications within 45 days of receipt of this letter.

This license amendment to incorporate the proposed Technical Specifications has been determined to be a Class III Amendment. You should submit the appropriate fee. ,

Sincerely, y<

2mv w t% bvnwN Dennis L. Ziemann, Chief Operating Reactors Branch #2 Division of Operating Reactors

Enclosure:

Model Technical Specifications cc w/ enclosure:

See next page 7 9197@.L911. ,

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Southern California Edison Canpany - 2*- August 28, 1978

) cc Rollin E. Woodbury, Vice President and General Counsel Southern California Edison Canpany Post Office Box 800 Rosemead, California 91770 David R. Pigott

. Samuel B. Casey

'Chickering & Gregory Three Dnbarcadero Center .

Twenty-Third Floor San Francisco, California 94111 .

David W. Gilman Robert G. Lacy San Diego Gas & Electric Company P. O. Box 1831 San Diego, California 92112 ,

Mission Viejo Branch Library 24851 Chrisanta Drive '

Mission Viejo, California 92676 4

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. ENCLOSURE EMERGENCY CORE COOLING SYSTEMS ,

ECCS SUBSYSTEMS - T4yg <275*F  :

LIMITING CONDITION FOR OPERATION 3.5.3 A maximum of one centrifugal charging pump and one high pressure injection pump shall be OPERABLE whenever the temperature of one or

' more of the RCS cold legs is <(275)'F.

SURVEILLANCE REQUIREMENTS 4.5.3 All charging pumps and safety injection pumps except those other-wise required to be OPERABLE shall be demonstrated inoperable at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> whenever the temperature of one or more of the RCS cold legs is <(275) F by verifying the motor circuit breakers have been removed from their electrical power supply circuits.

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' EMERGENCY CORE COOLING SYSTEMS , ENCLOSURE BASES _

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The limitation for a maximum of one high pressure safety injection pump to be OPERABLE and the Surveillance Requirement to verify all high pressure injection pumps except the required CPERABLE pump to be inoperable safety below (275) F provides assurance that a mass addition' pressure transient can be relieved by the operation of a single FORV. ,.

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ENCLOSURE REACTI'/ITY C0tlTROL SYSTEMS CHARGIt!G PUMP - SHUTCOWN

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LIMITING CONDITION FOR OPERATION 3.1. 2~. 3 One charging pump in the boron injection flow pat'h required by Specification (3.1.2.1) shall be OPERABLE and capable'of being powered from an OPERABLE emergency bus.

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. . APPLICABILITY: MODES 5 and 6.

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SURVEILLANCE REQUIREMENTS 4.1. 2. 3 All charging pumos, except the above required OPERABLE pump, shall be demonstrated inoperable at least once per 1?. hours verifying $

that the motor circuit breakers have been removed from their electrical '

power supply circuit;s.

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. . ENCLOSURE 3/4.1 REACTIVITY CONTROL SYSTEMS BASES -

3/4.1.1 BORATION SYSTEMS y-The limitations for a maximum of one centrifugal charging pump to be OPERABLE and the Surveillance Requirement to verify all charging pumps

• except the required OPERABLE pump to be inoperable below (27MV provides assurance that a mass addition pressure transient can be relieved by the operation of a single PORV.

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ENCLOSURE .

1 REACTOR C00LAt:T SYSTEM OVERPRESSURE PROTECTI0ti SYSTEMS

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LIMITUiG CCilDITI0ft FOR OPERATION

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3.4.9.3 At least one of the following overpressure protection systems '

shall be OPERABLE: .

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- a. Two power operated relief valves (PORVs) with a lift setting ,

of 1(450) psig, or

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b. A reactor coolant system vent of > ( ) square inches.

APPLICABILITY: 'dhen the temperature of one or more of the RCS cold legs

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is 1 (275)"F. ,,

ACTI0ft:

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a. [With one PORV inoperable, either restore the inoperable PORYto

- RCS thicugh a ( ) square inch vent (s) within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; .

maintain the RCS in a vented conditiert until both PORVs have been restored to OPER.aBLE stat s. -

b. With both PCRVs inoperable, depressurize and vent the RCS through a ( ) square inch vent (s) within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; maintain the RCS in a vented condition until both ,PORVs have been

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restored to OPE?ABLE status.

c. In the event either the PORVs or the RCS vent (s) are used to .

mitigate a RCS pressure transfent, a Special Report shall be prepared and submitted to the Ceraission pursuant to, , ,

Speci fi".tien 6.9.2 within 30 days. The report :na,i cescr u e '

the circumstances initiating the transient, the effect of the POP,Vs or vent (s) en the transient and any corrective action necessary to preverit recur ence. (

d. The provisions of Specification 3.0.4 are not apclicable. .

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- "l ENCLOSURE

. REACTOR C00LAt:T SYSTEM SURVEILLA!!CE REQUIREMEilTS

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4.4.9.3.1 Each PORV shall be demonstrated OPERABLE by:

a. Performance of a CHANf EL FUNCTIONAL TEST 'on the PORV actuatien channel, but excluding vaiva operation', within 31 days prior to entering a condition in which the PORV is required OPERABLE and at least once per 31 days thereaf ter when the PORV is required ,

OPERABLE. <

b. Performance of a CHAriMEL CALIBRATION on the PORY actuation ,

channel at least once per 18 months.

c. Verifying the POP.V isolation valve is open at least once per

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72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when the PORV is being used for overpressure pectaction. ,

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I d. Testing in accordance with the inservice test requirements for 1 ASME Category C values as specified in Section XI of the

, l f ASME, Boiler and Pressure Vessel Code 1974 Edition, and Addenda through Winter 1975. -

4.4.9.3.2 The RCS vent (s) shall be verified to be open at least cnce per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

• when the vent (t) is being used for overpressure protecti:n .

e ri "Except wnen tne vent pathway is provided with a valve wnich is locked,

- sealed, or other.tise secured in the ooen position, then verify thes2

, valves open at least once per 31 days.

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. .i ENCLOSURE 3/4.4 REACTOR C00LAr1T SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS -

NORMAL OPERATION ,

LIMITIf4G CONDITION FOR OPERATION A reactor coolant pump shall not be started with one or more of the RCS cold leg temperature <(275)*F unless 1) the pressurizer water ~

cubic feet or 2) the secondary water volume is less than temperature of each steam generator is less than *F above each .

of the RCS cold leg temperatures.

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- - ENCLOSURE REACTOR C00LAtlT SYSTEM BASES .

The OPERABILITY of two PORVs or an RCS vent opening of greater than

( ) square inches ensures that the RCS will be protected from pressure transients which cou]d exceed the limits of Appendix G to 10 CFR Part 50 when one or more of the RCS cold legs are <(275) F. Either PORV has adequate relieving capability to protect tfie RCS from overpressurization when the transient is limited to either (1) the start of an idle RCS with the secondary water temperature of the steam generator <( )*F above the RCS cold leg temperature or (2) the start of a HPSI pump and its injeccion into a water solid RCS.

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