ML20211D358

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Amend 115 to License NPF-1,changing Tech Spec 3/4.1.3 Per 851101 & 860128 Applications,To Allow Operation to Continue for 72 H for Diagnosis & Repair When One or More Control Rod Assemblies Electrically Inoperable
ML20211D358
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 05/29/1986
From: Varga S
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20211D350 List:
References
NUDOCS 8606120823
Download: ML20211D358 (7)
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Text

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d  %, UNITED STATES

{ g NUCLEAR REGULATORY COMMISSION t rj WASHINGTON, D. C. 20555

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PORTLAND GENERAL ELECTRIC COMPANY :y .

THE CITY OF EUGENE, OREGON l

PACIFIC POWER AND LIGHT COMPANY DOCKET NO. 50-344 TROJAN NUCLEAR PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 115 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., (the licensee) dated November 1,1985, as revised Taniiiry 28, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and 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 rules and 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 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 amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

8606120823 DR 860529 ADOCK 05000344 PDR

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2. Accordingly,thelicenseisamendedbychangestotheTechnical' 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. 115, 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 NUCLE TORY COMMISSION f f 6 A Dire t IPWR Project Directora e o. 3 Division of PWR Licens1 -A, NRR

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Attachment:

Changes to the Technical Specifications Date of Issuance: May 29, 1986 o

ATTACHMENT TO LICENSE AMENDMENT NO. 115 TO FACILITY OPERATING LICENSE NO. NPF-1 DOCKET NO. 50-344 Revise Appendix A as follows:

Remove Pages Insert Pages TS 3/4 1-19 TS 3/4 1-18

3/4 1-18a B 3/4 1-3 S 3/4 1-3 8 3/4 1-4 B 3/4 1-4 t

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REACTIVITY CONTROL SYSTEMS 3/4.1.3 h0VABLE CONTROL ASSEMBLIES GROUP HEIGHT LIMITING CONDITION FOR OPERATION 3.1. 3.1 All rods (shutdown and control) shall be OPERABLE and positioned within i 12 steps (indicated position) of their group step l counter demand po:ition.

APPLICABILITY: MODES 1* and 2*

ACTION:

The ACTION to be taken is based on the cause of inoperability of the control rods as follows:

ACTION l 3 .. More Than

.. CAUSE OF INOPERABILITY One Rod One Rod a) Immovable as a result of excessive (1) (1) friction or mechanical interference or known to be untrippable.

b) Misaligned from.its group step (4) (2)

. counter demand height or from any ,

. Other rod in its group by more than i 12 steps (indicated position).

c) Inopera'ble due to a rod control urgent (3) (3) failure alarm or other electrical problem in the rod control system, but trippable.

ACTION 1 - Determine that the SHUTDOWN MARGIN requirement of Specifica-tion 3.1.1.1 is satisfied within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 2 - Be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 3 - Restore the inoperable rods to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> l or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

]

  • See Special Exceptions 3.10.2 and 3.10.4.

ll TRO.1AN-UNIT 1 3/4 1-18 Amendment No. 7g ,115

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. REACTIVITY CONTROL SYSTEMS' LIMITING CONDITION FOR OPERATION ACTION 4 - POWER OPERATION may continue provided that within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either:

1. The rod is restored to OPERABLE status within the above alignment requirements, or
2. The rod is declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied. POWER OPERATION may then continue provided that:

a) An analysis of the potential ejected rod worth is performed within 3 days and the rod worth is deter-mined to be 5 0.98% Ak at zero power and S 0.21%

Ak at RATED THERMAL POWER for the remainder of the fuel cycle, and

. b) The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and fr.- c) The THERMAL POWER level is reduced to S 75% of RATED THERMAL POWER WITHIN one hour and within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the high neutron flux trip setpoint is reduced to 185% of RATED THERMAL POWER, or d) The remainder of the rods in the group with the inoperable rod are aligned to within ! 12 steps of the inoperable rod within one hour while maintaining

.- the ro'd sequence and insertion limits of Figures 3.1-1 and 3.1-2; the THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.5 during subsequent operation.

SURVEILLANCE REOUIREMENTS 4.1. 3.1.1 The position of each rod shall be determined to be within the l group demand limit by verifying the individual rod positions at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the Rod Position Deviation Monitor is inoperable, then verify the group positions at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

4 .1. 3.1. 2 Each rod not fully inserted shall be determined to be OPERABLE by l movement of at least 10 steps in any one direction at least once per 31 days.

ll TROJAN-UNIT 1 3/4 1-18a Amendment No.16,115 e

_ REACT!vlTY CONTROL SYSTFMS, BASES 3/4.1.2 BORATION SYSTEMS (Continued) without single failure consideration on the basis of the condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity :.hange in the event the single injection system becomes inoperable.

for an inadvertent positive reactivity addition to the Reacto maintain 200*F to 80*F. a constant RCS reactivity while the temperatur l boron concentration to compensate for an inadvertent pos addition of approximately 1 percent ak/k while in the refueling mode.

r the boric acid storage tanks or 23,432 usable gallons of water from the refueling water storage tank.

incriased to a value greater than the minimum level indic gallons), to g235 gallons.

The required RWST volume of 23,432 gallons must be increased to account for nonusable volume due to tank geometry, letdown and vortexing co'nsiderations (78,000 gallons), to101,432 gallons (rounded to 102,000 gallons).

3/4.1.3 MOVABLE C NTROL ASSEMBLIES The specifications of this section ensure that (1) acceptable power distribution limits are maintained, (2) the minimum SHUTDOWN MARGIN is main-tained, and (3) the potential effects of a rod ejection accident are limited

- OPERABILITY of the control rod position indicators is required to determine .

control rodand alignment positions and insertion thereby ensure compliance with the control rod limits.

i movability of a control rod invokes ACTIONBefore Statement 3.1.3.

utilizing ACTION Statement 3.1.3.1.c. the rod control urgent failure alarm must controlbe illuminated or an electrical problem must be detected in the rod system.

OPERABLE during the last performance of Surveillance Require ..

and met the rod drop time criteria of Specification 3.1.3.3 during the last performance of Surveillance Requirement 4.1.3.3.

TROJAN-UNIT 1 B 3/4 1-3 Amendment No. 18, W , 115

REACTIVITY CONTROL SYSTEMS BASES 3/4.1.3 MOVABLE CONTROL ASSEMBLIES (Continued) -

The ACTION statements which permit limited variations from'the basic requirements are accompanied by additional restrictions which ensure that the original criteria are met. Misalignment of a rod requires measurement l of peaking factors or a restriction of THERMAL POWER; either of these  !

restrictions provides assurance of fuel rod integrity during continued )

operation. The reactivity worth of a misaligned rod is limited for the remainder of the fuel cycle to prevent exceeding the assumptions used in the accident analysis for a rod ejection accident.

The maximum rod drop time restriction is consistent with the assumed rod drop time used in the accident analyses. Measurement with Tavg >550'F and with all reactor coolant pumps operating ensures that the measured drop times will be representative of insertion times experienced during a reactor trip at operating conditions.

Control rod positions and OPERABILITY of the rod position indicators

, are required to be verified on a nominal basis of once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with more frequent verifications required if an automatic monitoring channel is inoperable. These verification frequencies are adequate for assuring that the applicable LCO's are satisfied.

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TROJAN-UNIT 1 8 3/4 1-4 Amendment No. 18 //1 , 115 d

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