ML20063B787

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Amend 1 to License NPF-10,clarifying Tech Spec Setpoint Requirements for Shutdown Cooling Sys Relief Valve
ML20063B787
Person / Time
Site: San Onofre Southern California Edison icon.png
Issue date: 03/30/1982
From: Miraglia F
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20063B790 List:
References
NUDOCS 8205030006
Download: ML20063B787 (5)


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SOUT!!ER1 CALIFORMI A EDISON C0rPANY SA!! DIEGO GAS AND ELECTRIC C0!PANY T!!E CITY OF RIVERSIDE CALIFORNIA Tile CITY OF ANA4EIM, CALIFORNI A DOCKET t10. 50-361 SAN 040FRE fluCLEAR GEtiERATING STATI0'l, UNIT 2 ATNDHENT TO FACILITY OPERATING LICENSE Anendment No. 1 License No. NPF-10 1.

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

A.

The apolication for anendment to the San Onofre Nuclear Generating Station, Unit 2 (the facility) Facility Operatinq License No. NPF-10 filed by the Southern California Edison Connany on behalf of itself and San Otego Gas and Electric Cmpany, The City of Riverside and The City of Anaheia, California (licensees) dated flarch 12, 1982, conplies with the standards and requirements of the Atomic Energy Act of 1954, s

as ataended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Comission; C.

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

safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this license anendment will not be inimical to the comian defense and security or to the health and safety of the public; E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Cox11ssion's regulations and all applicable requirements have been satisffed.

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p l 2. - Accordingly, the license is amended by changes to the Technical Specifica--

tions as indicated in the attachnent to this license amendment, and paragraph 2.C(2) of Facility Operating License No. HPF-10 is hervty amended to read as follow:

(2) Technical Specifications The Technical Specifications contained in Apoencix A and the Environ-nental Protection Plan contained in. Appendix B, as revised throuqh Amendment No.1, are hereby incorporated in the license-SCE shall operate the facility in accordance with the Technic?1 Specifications and the Environemtnal Protection Plan.

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This license a'.le.uinent is effective as of !! arch 13, 1982.

FOR THE flVCLEAR REGULATORY C0't?11SS10M Original signed by,

/5 / Frank J. Miraglia Frank J. ttiraglia, Chief Licensing Branch t!o. 3 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance:

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ATTACHMENT TO LICENSE AMENINENT NO.1 FACILITY OPERATING LICENSE NO. NF-10 DOCKET NO. 50-361 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number-and contain vertical lines indicating the area of change. The corresponding ovem leaf pages are also provided to main document completeness.

Overleaf Amended Page Page 3/44-31 3/44-32 3/44-34 3/44-33 o

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REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS RCS TEMPERATURE > 235 F LIMITING CONDITION FOR OPERATION 3.4.8.3.2 At least one of the following overpressure protection systems shall be OPERABLE:

The Shutdown Cooling System (SDCS) Relief Valve (PSV 9349) with a a.

setting of 406 + 10 psig**, or, b.

A minimum of one pressurizer code safety valve with a lif t setting of 2500 psia + 1%^.

APPLICABILITY:

MODE 4 with RCS temperature above 235 F.

ACTION:

With no safety or relief valve operable, be in COLD SHUTDOWN and vent the RCS through a greater than or equal to 5.6 square inch vent within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.4.8.3.2.1 The SDCS Relief Valve shall be demonstrated OPERABLE by:

a.

Verifying at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> that the SDCS Relief Valve isolation valves are open when the SDCS Relief Valve is being used for overpressure protection.

b.

Testing pursuant to Specification 4.0.5 with an inservice test interval of at least once per 30 months.

4.4.8.3.2.2 The pressurizer code safety valve has no additional surveillance requirements other than those required by Specification 4.0.5.

4.4.8.3.2.3 The RCS vent shall be verified to be open at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the vent is being used for overpressure protection, except when the vent pathway is provided with a valve which is locked, sealed, or otherwise secured in the open position, then verify these valves open at least once per 31 days.

'The lif t setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.

    • For relief valve temperatures less than or equal to 130*F.

1 SAN ONOFRE-UNIT 2 3/4 4-33 AVINDENT NO.1

i' REACTOR COOLANT SYSTEM

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3.4.9 STRUCTURAL INTEGRITY l

LIMITING CONDITION FOR OPERATION 3.4.9 The structural integrity of ASME Code Class 1, 2 and 3 components shall be maintained in accordance with Specification 4.4.9.

APPLICABILITY:

ALL MODES ACTION:

With the structural integrity of any ASME Code Class 1 component (s) a.

i not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature more than 50*F above the minimum temperature required by NDT considerations.

b.

With the structural integrity of any ASME Code Class 2 component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature above 200 F.

With the structural integrity of any ASME Code Class 3 component (s) c.

not conforming to the above requirements, restore the structural integrity of the affected component to within its limit or isolate the affected component from service.

d.

The provisions of' Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.4.9 In addition to the requirements of Specification 4.0.5, each Reactor Coolant Pump flywheel shall be inspected per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975.

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SAN ONOFRE-UNIT 2 3/4 4-34

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RE' ACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS RCS TEMPERATURE I 235 F

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LIMITING CONDITION FOR OPERATION 3.4.8.3.1

  • At least one of the following overpres'sure protection systems shall be OPERABLE:

The Shutdown Cooling System (SDCS) Relief Valve (PSV9349) with a a.

lift setting of 406 + 10 psig*, or, b.

The Reactor Coolant System depressurized with an RCS vent of greater than or equal to 5.6 square inches.

APPLICABILITY:

H0DE 4 when the temperature of cne any RCS cold leg is less than or equal to 235 F; Mode 5; Mode 6 with the reactor vessel head on.

ACTION:

With the SDCS Relief Valve inoperable, reduce i to less than a.

200 F, depressurize and vent the RCS through a greater than or equal to 5.6 square inch vent within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

b.

With one or both SDCS Relief Valve isolation valves in a single-SDCS Relief Valve isolation valve pair (valve pair 2ilV9337 and 2HV9339 or valve pair 2fiV9377 and 2HV9378) closed, open the closed valve (s) within 7 days or reduce T to less than 200 F, depres-surize and vent the RCS through a @@ater than or equal to 5.6 inch vent within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

In the event either the SDCS Relief Valve or an RCS vent is used to c.

mitigate a RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days.

The report shall describe the circumstances initi-ating the transient, the effect of the SDCS Relief Valve or RCS vent on the transient and any corrective action necessary to prevent recurrence.

d.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS

4. 4. 8. 3.1.1 The SDCS Relief Valve shall be demonstrated OPERABLE by:

Verifying at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when the SDCS Relief Valve is a.

being used for overpressure protection that at least one pair of SDCS Relief Valve isolation valves (vcive pair 2HV9337 and 2HV9339 or valve pair 2HV9377 and 2HV9378) is open.

  • Fur relief valve temperatures less than or equal to 130*F.

SAN ONOFRE-UNIT 2 3/4 4-32 AMENLIENT NO.1

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REACTOR COOLANT SYSTEM l

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PRESSURIZER s._-

LIMITING CONDITION FOR OPERATION 4

4 3.4.8.2 The pressurizer temperature shall be limited to:

a.

A maximum heatup of 200*F in any one hour period, i

t b.

A maximum cooldown of 200 F in any one hour period.

APPLICABILITY: At all times.

3 ACTION:

With the pressurizer temperature limits in excess of any of the above limits, restore the temperature to within the limits within 30 minutes; perform an engineering evaluation to determine the effects of the out-of-limit condition on the structural integrity of the pressurizer; determine that the pressurizer remains acceptable for continued operation or be in at least HOT STANDBY within t_he next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce the pressurizer pressure to less than 500 psig within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

t SURVEILLANCE REQUIREMENTS 1

4.4.8.2.1 The pressurizer temperatures shall be determined to be within the limits at least once per 30 minutes during system heatup or cooldown.

i 4.4.8.2.2 The spray water temperature differential shall be determined for use in Table 5.7-1 at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during auxiliary spray operation.

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