ML20237G532

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Amends 17 & 16 to Licenses DPR-80 & DPR-82,respectively, Changing Tech Specs to Revise Steam Generator Water Level Low Reactor Setpoint from 25% to 15% of Narrow Range Instrument Span
ML20237G532
Person / Time
Site: Diablo Canyon  
Issue date: 08/27/1987
From: Knighton G
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20237G534 List:
References
TASK-2.D.1, TASK-TM TAC-51590, TAC-64905, TAC-64906, NUDOCS 8709020295
Download: ML20237G532 (7)


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PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-275 I

1 AMENDMENT TO FACILITY dPERATING LICENSE Amendment No.17 License No. DPR-80 l

l 1.

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

A.

The application for amendment by Pacific Gas & Electric Company (the licensee) dated March 13, 1987 as supplemented July 9, 1987, complies with the standards and requirements of the Atomic Energy

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Act of 1954, as amended (the Act), and -the Comission's regulations i

set forth in 10 CFR Chapter I; i

B.

The facility will o>erate in conformity with the ap)11 cation, the provisions of tie Act, and the regulations of t1e Comission; 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 Comission'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. DPR-80 is hereby amended to read as follows:

1 (2) Technical Specifications I

The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 17, are hereby incorporated in the license.

Pacific Gas & Electric Company shall operate the facility in

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accordance with the Technical Specifications and the Environmental-Protection Plan, except where otherwise stated in specific license conditions, i

3.

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

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FOR THE NUCLEAR REGULA ORY COMMISSION M lh i

' George y Knighton, rector Projec Directora 1

Division of Reactor Projects - III, I

l IV, V and Special Projects l

Attachment:

j Changes to the Technical Specifications Date of Issuance: August 27, 1987 l

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pa osong'o, UNITED STATES 1

NUCLEAR REGULATORY COMMISSION 7,,

E WASHINGTON, D. C. 20555

%,...l.. l PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLANT, UNIT 2

'l DOCKET N0. 50-323 j

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.16 License No. DPR-82 l

1.

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

A.

The application for amendment by Pacific Gas & Electric Company (the licensee) dated March 13, 1987, as supplemented July 9, 1987, 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;

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B.

The facility will caerate in conformity with the ap)liettion, the provisions of tie Act, and the regulations of tie 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 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.

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4 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. DPR-82 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 No.

16, 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 C0t@ilSSION l l & '~ f M '

4 eorge W.'

nighton, ector Projectt'irectorate Division of Reactor Projects - III, IV, Y and Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance: August 27, 1987

August 27, 1987 4

ATTACHMENT TO LICENSE AMENDMENT NOS.17 AND 16 FACILITY OPERATING LICENSE NOS. DPR-80 AND DPR-82 DOCKET NOS. 50-275 AND 50-323 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.

Remove Insert 2-5 2-5 B 2-7 B 2-7 l

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N LIMITING SAFETY SYSTEM SETTINGS BASES 1

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y Steam Genitator Water Level,

The; Steam W erator Water Level Lew-Low trip protects the reactor from ioss of heat sitik in the events of'a sustained steam /feedwater flow mismatch resulting fr3m loss of normal feedwatav.

The specified Setpoint provides alloontes fos s' tarting delays of.the Auxiliary Feedwater System.

Steam /Feedwater Flow Misdatchland Low Steam Benerator Water Level TN Steam /F9edwate'r flow Nsmatch in coincidence with a Steam Generator Low War.er Leve %tnip is not used in the trnnsient and accident analyses but is included in Tame 2.2'1 to e'nsure the functional capability of the specified trip settings and therebysenbance, the'oYerall reliability of the Reactor Trip System.

This trip is redandant to'the Steam Generator Water Level Low-Low trip.

The Steam /Foc& ater-Flow Mismatch portion of this trip is activated when s

the steam flow-egceeds th'e 14edwater flow by greater than or equal to 1.45 x 10 6

'bs/hr for Un.i M and 1.49 ( 106 lbs/hr for Unit 2.

The Steam Generator Low Water level portion of the if fp' ig activated when the water level drops below 15%, as indicated by tue narrow ra.3ge instrument..These trip values include l

sufficient allowance in excess of normal operating' values to preclude spurious trips but will initiate a Reactor trip before the steam generators are dry.

Therefort(the required capacity and starting time requirements of the auxiliary feedwater pumps are reduced and the:Resulting thermal transient on the Reactor Coolant System and steam generators 9 minicized.

Undervoltage and Underfrequency - Reactor Coolant Pump Busses s

Tht'UnderWitage _and Underfrequency Reactor Coolant Pump Bus trips provide core proEe'ctior,",against DNB as a result of complete loss of forced coolant flow.

The specified'0etpoints assure a Reactor trip signal is generated before the Low Flow Trip Setpofnt is reached.

Time delays are incorporated in the Under-l frequendy and (Mdervoltage trips to prevent s prious Reactor trips from momen-l tary e10ctrical poder transients.

For undervoltage., the delay is set so that the time required for a' signal ?,o reach the Reactor trip breakers following the not exceed 0.h[ seconds. simultaneous t ip 16 two or mor6'reaEtor coolant pump bus circ For underfrequency, the delay is set so that the; time reqtired for a signal to reach the Reactor trip breakers after the Underfrequen-cy Trip Setpoint in reached shall not exceed 0.3 seconds.

On decreasing power, the Undervoltage dd Unddfrsquency Reactor Coolant Pump Bus trips are automa-tically blocked by 'P-7 (a power level of approximately 10% of RATED THERMAL POWER with a turbine impulse chamber pressure at approximately 10% of full power equivalents and on it. creasing power, reinstated automatically by P-7.

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1 DIABLO CANYON - UNITS 1 & 2 B 2-7 Amendment Nos.17 and If)

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