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Amends 27 & 26 to Licenses DPR-80 & DPR-82,respectively, Revising Limiting Conditions for Operation of Pressurizer PORVs & Clarifying Requirements for Startup Repts
	ML20148D625
Person / Time
Site:	Diablo Canyon
Issue date:	01/05/1988
From:	Knighton G; Office of Nuclear Reactor Regulation
To:	;
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ML20148D628	List: ML20148D625;
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	NUDOCS 8801250444
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UNITED STATES 8'

?,'n NUCLEAR REGULATORY COMMISSION

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WASHING TON, D. C. 20555

,o PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLANT, UNIT 1 DOCKET N0. 50-275 AMENDMENT TO FACILITY OPERATIN_G LICENSE Amendment No. 27 License No. DPR-80 1.

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

A.

The application for anendment by Pacific Gas & Electric Company (the licensee) dated October 24, 1985 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's 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 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 Commission's regulations; D.

The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.

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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) of Facility Operating License No. OPR-80 is hereby amended to read as follows:

(2) Technical _ Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment flo.

27, are hereby incorporated in the license.

Pacific Gas & Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions.

3.

This license amendment l'ecomes effective at the date of its issuance.

FOR THE NUCLEAR PEGULATORY COMMISSION I

George W. Knighton, Director Project Directorate V Division of Reactor Projects - III, IV, V and Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance: January 5, 1988 l

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UNITED STATES NUCLEAR REGULATORY COMMISSION

p WASHINGTON, D. C. 20555

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PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLANT, UNIT 2 OOCKET NO. 50-323 AMENDNENT TO FACILITY OPERATING LICENSE Amendment No. 26 License No OPR-82 1.

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

A.

The application for amendnent by Pacific Gas & Electric Company (the licensee) dated October 24, 1985 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Comission's 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 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 the common defense and security or to the health and safety of the public; and E.

The issuance of this amenament is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requiren:ents have been satisfied.

2-2.

Accordingly, the license is arsaded be changes to rise Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facilit', Operating L::cente No. OPR-82 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A ana the Environmental Protection Plan contafred in Appendix 6, as revised through Amendment fio.

26, are hereby incorporated in the license.

Pacific Gas & Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions.

3.

This license amendment becomes effective at the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSI0ff If I}

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George W. Vnighton, Director Project Directorate V Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

January 5,1988

January 5, 1988 ATTACHMENT T0 LICENSE AMENDMENT NOS. 27 AND 26 FACIL ITY OPERAT)NG LICENSE NOS. OPR-80 AND DPR-82 DOCKET NOS. 50-275 AND 50-323 Replace the followir.g 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.

Pemove Insert 3/4 4-10 3/4 4-10 3/4 4-10a B 3/4 4-2 B 3/4 4-2 B 3/4 4-2a 6-16 6-16

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REACTOR COOLANT SYSTEM 3/4.4.4 RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.4 All power operated relief valves (PORVs) and their associated block valves shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

With one or more PORV(s) inoperable because of excessive seat leakage, l

a.

within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the PORV(s) to OPERABLE status or close the associated block valve (s); otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

With one or more PORV(s) inoperable due to causes other than excessive seat leakage, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the PORV(s) to OPERABLE status or close the associated block valve (s) and remove power from i

the block valve, and 1.

With only one Class 1 PORV OPERABLE, restore at least a total of two Class 1 PORVs to OPERABLE status within the following 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , or 2.

With no Class 1 PORVs OPERABLE, restore at least one Class 1 PORV to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and follow ACTION b.1, above, with the time requirement of that ACTION statement based on the time of initial loss of the remaining inoperable Class 1 PORV or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUT 00WN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

With one or more block valve (s) inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months c.

1.

Restore the block valve (s) to OPERABLE status, or 2.

Close the block valve (s) and remove power from the block valve (s),

or 1

3.

Close the PORV(s) and remove power from its associated solenoid.

Also, comply with ACTION b, as appropriate, for the isolated PORV(s).

d.

The provisions of Specification 3.0.4 are not applicable.

DIABLO CANYON - UNITS 1 & 2 3/4 4-10 N4ENDMENT'NOS. 27 AND 26

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l REACTOR COOLANT SYSTEM i

SURVEILLANCE REQUIREMENTS 4.4.4.1 In addition to the requirements of Specification 4.0.5, each PORV shall be demonstrated OPERABLE at least once per 18 months by:

Operating the valve through one complete cycle of full travel, and a.

b.

Performing a CHANNEL CALIBRATION of the actuation instrumentation.

4.4.4.2 Each block valve shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel unless the block valve is closed in order to meet the requirements of ACTION a. and b.

in Specification 3.4.4.

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DIABLO CANYON - UNITS 1 & 2 3/4 4-10a AMENDMENT N05. 27 AND 26

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REACTOR COOLANT SYSTEM BASES SAFETY VALVES (Continued)

In the event that no safety valves are OPERABLE, an operating RHR loop, con-nected to the RCS, provides overpressure relief capability and will prevent RCS overpressurization.

In addition, the Overpressure Protection System (relief valves) provides a diverse means of protection against RCS overpressurization at low temperatures.

During operation, all pressurizer Code safety valves must be OPERABLE to prevent the RCS from being pressurized above its Safety Limit of 2735 psig.

The combined relief capacity of all of these valves is greater than the maximum surge rate resulting from a complete loss of load assuming no Reactor trip until the first Reactor Trip System Trip Setpoint is reached (i.e., no credit is taken for a direct Reactor trip on the loss of-load) and also assuming no operation of the power-operated relief valves or steam dump valves.

Demonstration of the safety valves' lift settings will occur only during shutdown and will be performed in accordance with the provisions of Section XI of the ASME Boiler and Pressure Code.

3/4.4.3 PRESSURIZER The limit on the maximum water volume in the pressurizer assures that the parameter is maintained within the normal steady-state envelope of operation assumed in the SAR.

The limit is consistent with the initial SAR assumptions.

The 12-hour periodic surveillance is sufficient to ensure that the parameter is restored to within its limit following expected transient operation.

The maximum water volume also ensures that a steam bubble is formed and thus the RCS is not a hydraulically solid system.

The requirement that a minimum number of pressurizer heaters be OPERABLE enhances the capability of the plant to control Reactor Coolant System pressure and establish natural circulation.

3/4.4.4 RELIEF VALVES The power-operated relief valves (PORVs) and steam bubble function to relieve RCS pressure during all design transients up to and including the design step load decrease with steam dump. Operation of the power-operated relief valves minimizes the undesirable opening of the spring-loaded pressurizer Code safety valves.

Each PORV has a remotely operated block valve to provide a positive shutoff capability should a relief valve become inoperable.

The PORVs perform a safety-related function by providing an RCS depres-surization path during certain event recovery sequences.

The capability of the PORVs to perform this function is based on manual actuation and does not require the pressure setpoint function of the valve to be OPERABLE in order to meet its limiting condition for operation.

DIABLO CANYON - UNITS 1 & 2 B 3/4 4-2 AMENDMENT NOS. 27 AND 26

e REACTOR COOLANT SYSTEM BASE 5 3/4.4.5 STEAM GENERATORS The Surveillance Requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the RCS will be main-tained.

The program for inservice inspection of steam gennrator tubes is based on a modification of Regulatory Guide 1.83, Revision 1.

Inservice inspect. ion of steam generator tubing is essential in order to maintain surveil-lance of the conditions of the tubes in the event that there is evidence of DIABLO CANYON - UNITS 1 & 2 B 3/4 4-2a AMENDMENT NOS. 27 AND 26

ADMINISTRATIVE CONTROLS 6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Regional Administrator of the Regional Office of the NRC unless otherwise noted.

STARTUP REPORTS

6. 9.1.1 A summary report of plant startup and power escalation testing shall be submitted following:

(1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9.1.2 The initial Startup Report shall address each of the startup tests identified in Chapter 14 of the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications.

Any corrective actions that were required to obtain satisfac-tory operation shall also be described.

Any additional specific details required in license conditions based on other commitments shall be included in this report.

Subsequent Startup Reports shall address startup tests that are necessary to demonstrate acceptability of the change and/or modification.

6.9.1.3 Startup Reports shall be submitted within:

(1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.

If the Startup Report does not cover all three events (i.e., initial criticality, completion of Startup Test Program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

ANNUAL REPORTS

6.9.1.4 Annual Reports covering the activities of the unit as described below during the previous calendar year shall be submitted prior to March 31 of each The initial report shall be submitted prior to March 31 of the year year.

following initial criticality.

Reports required on an annual basis shall include a tabulation on an annual basis of the number of station, utility and other personnel (including contrac-tors) receiving exposures greater than 100 mrem /yr and their associated man

A single submittal may be made for a multiple-unit plant.

The submittal should combine those sections that are common to all units at the plant.

DIABLO CANYOH - UNITS 1 & 2 6-16 AMENDMENT NOS, 27 AND 26 t

ML20148D625

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