ML20154D484

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Amend 142 to License NPF-1,permitting Relief from Limiting Condition for Operation 3.0.4 for Tech Spec Sections 3.2.4, 3.9.2,3.9.7,3.9.9 & 3.9.11 Re Power Distribution
ML20154D484
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 05/11/1988
From: Knighton G
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20154D473 List:
References
NUDOCS 8805190209
Download: ML20154D484 (9)
v • d • e


Text

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. d 'o UNITED STATES

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!" n NUCLEAR REGULATORY COMMISSION

(, WASHINGTON, D. C. 20555

%, ,o PORTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE, OREGON PACIFIC POWER AND LIGHT COMPANY DOCKET N0. 50-344 TROJAN NUCLEAR PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No 142 License No. NPF-1

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

A. The application for amendment by Portland General Electric Company, et al. (thelicensee)datedAugust 16, 1985 as revised December 19, '

T78 Fan,d April 20, 1988, 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 cperate in conformity with the application, the previsions of the Act, and the regulations of the 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 Coninission'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 opplicable requirements i have been satisfied.

8805190209 G00511 PDR A00CK 00000344 P PDR

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. NPF-1 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.142, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifica-tions, except where otherwise stated in specific license conditions.

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

FOR THE NUCLEAR REGULATORY COMMISSION eorge . Kn ght , Director Project Directorate V Division of Reactor Projects - i!I, IV, Y and Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance: May 11, 1988 i _ __ _ _ _ _ _ _ _ _ _ _

ATTACHMENT TO LICENSE AMENDMENT N0. 142 TO FACI'.ITY OPERATING LICENSE N0. NPF-1 DOCKET NO. 50-344 Revise Appendix A as follows:

Remove Pages Insert Pages 3/4 2-11 3/4 2-11 3/4 9-2 3/4 9-2 3/4 9-7 3/4 9-7 3/4 9-9 3/4 9-9 3/4 9-11 3/4 9-11 I

6-14a 6-14a  ;

6-16 6-16  !

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6-17 6-17 i

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POWER OISTRIBUTION LIMITING CONDITION FOR OPERATION (Continued)

2. Verify that the QUADRANT POWER TILT RATIO is within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after exceeding the li.mit or reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and reduce the Power Range Neutron Flux-High trip Setpoints to 5 55% of RATED THERNAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
3. Identify and correct the cause of the out of limit con-dition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50% of RATED THERMAL POWER may proceed provided that the QUADRANT POWER TILT RATIO is verified within its limit at least once per hour until verified acceptable at 95% or greater RATED THERMAL POWER.
c. With the QUADRANT POWER TILT RATIO determined to exceed 1.09 due to causes other than the misalignment of either a control or shutdown rod:
1. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and reduce the Power Range Neutron Flux-High Trip Setpoints to 5 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
2. Identify and correct the cause of the out of limit con-dition prior to increasing THERMAL POWER: subsequent POWER OPERATION above 50% of RATED THERMAL POWER may proceed provided that the QUADRANT POWER TILT RATIO is verified within its limit at least once per hour until verified at 95% or greater RATED THERMAL POWER,
d. The provisions of Specification 3.0.4 are not applicable. l SURVEILLANCE REQUIREMENTS )

4.2.4 The QUADRANT POWER TILT RATIO shall be determined to be within the ,

limit above 50% of RATED THERMAL POWER by:  !

a. Calculating the ratio at least once per 7 days.when the alarm is OPERABLE.
b. Calculating the ratio 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 steady state operation when the alarm is inoperable.
c. Using the movable incore detectors to determine the QUADRANT POWER TILT RATIO 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 one Power Range Channel is inoperable & THERMAL POWER is > 75 percent of RATED THERMAL POWER. .

TROJAN-UNIT 1 3/4 2-11 Amendment No. J9,142 May 11, 1988

LCA 126

. Attachment 1

. Page 8 of 11 REFUELING OPERATIONS INSTRUMENTATION LIMITING CONDITION FOR OPERATION

'3.9.2 As a minimum, two source range neutron flux monitors shall be operating, each with continuous visual indication in the control room and one with audible indication in the containment.

APPLICABILITY: MODE 6.

ACTION:

Witn the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity 1 changes. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.2 Each source range neutron flux monitor shall be demonstrated OPERABLE by performance of:

a. A CHANNEL FUNCTIONAL TEST at least once per 7 days, and
b. A CHANNEL FUNCTIONAL TEST within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to the initial start of CORE ALTERATIONS, and
c. A CHANNEL CHECK 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 CORE ALTERATIONS.

l TROJAN-UNIT 1 3/4 9-2 Anandment No. 142 May 11, 1988

l REFUELING OPERATIONS j CRANE TRAVEL - FUEL BUILDING LIMITING CONDITION FOR OPERATION ,

I 3.9.7 Loads carried over the spent fuel pool and the heights at which they may be carried over racks containing fuel shall be limited in such I a way as to preclude impact energies over 240,000 in.-lbs, if the loads l are dropped. I APPLICABILITY: With fuel assemblies and water in the storage pool.

ACTION:

With the requirements of the above specification not satisfied, place the crane load in a safe condition. The provisions of Specification 3.0.3 and 3.0.4 are not applierM

  • SURVEILLANCE REQUIREMENTS 1

4.9.7 The potential impact energy due to dropping the crane's load shall I be detent.ined to be 5 240,000 in.-lbs prior to moving each load over f racks containing fuel. '

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l TROJAN-UNIT 1 3/49-7 Amendment No. 3M ,142 May 11, 1988

I REFUELING OPERATIONS CONTAINMENT VENTILATION ISOLATION SYSTEM LIMITING CONDITION FOR OPERATION 3.9.9 The Containment Ventilation isolation system shall be OPERABLE.

APPLICABILITY: MODE 6 ACTION:

With the Containment Ventilation isolation system inoperable, close each of the penetrations providing direct access from the containment atmosphere to the outside atmosphere. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS  ;

4.9.9 The Containment Ventilation isolation system shall be demonstrated OPERABLE within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of and at least once per 7 days during CORE ALTERATIONS by verifying that Containment Ventilation isolation occurs on manual initiation and on a high radiation signal from each of the containment process radiation monitoring instrumentation channels.

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l l TROJAN-UNIT 1 3/4 9-9 Amendment No. 142 May 11, 1988

REFUELING OPERATIONS STORAGE POOL WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.11 As a minimum, 23 feet of water shall be maintained over the top of irradiated fuel assemblies seated in the storage racks.

APPLICABILITY: Whenever irradiated fuel assemblies are in the storage pool.

ACTION:

With the requirement of the specification not satisfied, suspend all movement of fuel and crane operations with loads in the fuel storage areas and restcre the water level to within its limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

l SURVEILLANCE REQUIREMENTS 4.9.11 The water level in the storage pool shall be determined to be at least its minimum required depth at least once per 7 days when irradiated fuel assemblies are in the fuel storage pool.

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l TROJAN-UNIT 1 3/4 9-11 Amendment No. 142 May 11, 1988 l

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, May 11, 1988 ATTACHMENT TO LICENSE AMEN 0 MENT NO. 142 TO FACILITY OPERATING LICENSE NO. NPF-1 I

DOCKET NO. 50-344 Revise Appendix 8 as follows: j Rernove Pages Insert Pages 5-2 5-2 l

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