ML20008G052
| ML20008G052 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 06/23/1981 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20008G051 | List: |
| References | |
| NUDOCS 8107020062 | |
| Download: ML20008G052 (8) | |
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1.12 _.. jf PORTLAND GENERAL ELECi?.IC COFDA4Y TIE CITY OF E"CCN:. 0.1ECOM PACIFIC POWER AND LIGHT COMPANY DOCKET N0. 50-344 TROJAN NUCLEAR PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 64 License No. NPF-1 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Portland General Electric Company, the City of Eugene, Oregon, and Pacific Power and Light Company (the licensee) dated March 16, 1981, and supplemental letter dated November 26, 1980, complies with the standards and requirements of the itomic Energy Act of 1954, as amended (the Act) and the Commission'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 Commission; C.
There is reasonable assurance (i) that the activities authorized i
by this imendment 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; f
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 l
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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- rdir. gly, th: li: ente is mended L; ht 095 t^ th+ T+Ch'ical Specifications as incicated in Inc ::::chmen; tu this license amendment, anc paragraph 2.C.(2) cf :::ility Operating License at fnlinws:
'!0. $!PF-1 is herehy amended to read (2) Technical Specifications The Technical Specifications conteined in Appendices A and B, as revised through Amendmant No. 64, are hereby incorporated in the license. The licensee shall operate the facility in accordanca with the Technical Specifications, except as noted in paragraph 2.C.(10) throu~gh 2.C.(12) below.
3.
This license amendment is effective as of tne date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Robert A.' Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: June 23, 1981 i
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. AMEj 0ME!!! ~ !!U. 6: TO FACILITY OPEr.a.Tm.i.: t.1CEn5E nu. NPF-i DOCKET NO. 60 '4aa Revise Appendix A as follows:
Remove Pages Insert Pages III III 3/4 1-1 3/4 1-1 3/4 1-2 3/4 1-2 3/4 1-3 3/4 1-3 8 3/4 1-1 B 3/4 1-1 1
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((LIMITINGCONDITIONSFOROPE?.ATIONANDSURVEILLANCEREQUIREMENTS si
- l ll SECTION Page II ll 3/4.0 APPLICABILITY..........................................
3/4 0-1 ll3/4.1 REACTIVITY CONTROL SYSTEMS I!;, 3/4.1.1 BORATION CONTROL ll S h u t d own Ma rg i n.....................................
3/4 1-1 t'
B o ro n D il u ti o n......................................
3/4 1-4 l
11 Mode ra tor Tempe ra ture Coe f ficient...................
3/4 1-5 11 11 Mi nimum Temperature for Cri ti cal i ty.................
3/4 1-6 la l
l-3/4.1.2 BORATION SYSTEMS Fl ow Pa th s - Sh u td own...............................
3/4 1-7 Fl ow Pa th s - 0'p e ra ti ng..............................
3/4 1-9 Charging Pump - Shutdown............................
3/4 1-11 Chargi ng Pumps - Ope rati ng..........................
3/4 1-12 Boric Acid Trans fer Pumps - Shutdown................
3/4 1-13 Boric Acid Trans fer Pumps - Operati ng...............
3/4 1-14 Borated Water Sources - Shutdown....................
3/4 1-15 Borated Wa ter Sources - Operati ng...................
3/4 1-16 3/4.1.3 MOYABLE CONTROL ASSEMBLIES Group Height..................
3/4 1-18 I
Posi tion Indicator Channel s........................
3/4 1-20 Rod Drop Time.......................................
3/4 1-21 Shutdown Rod Inse rti on Limi t........................
3/4 1-22 Control Rod In sertion Limi ts........................
3/4 1-23 f
Pa rt length Rod Insertion Limi ts....................
3/4 1-26 TROJAN-UNIT 1 III Amendment No. 64
M1 P.EACTIVITY CON THut d u e ii
!!3/~.1.1 CORATION 00?Tn0L i;
l{SHu(DOWNMARGI4 l
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LIMITING CONDITION FOR OPERATI0f4 i
3.1.1.1 The SHUTDOWN MARGIN sh:1! be 2 1.6" ak/k.
APPLICABILITY: MODES 1, 2*,
3, 4, c.d 5.
ACTION:
With the SHUTDOWN MARGIN < 1.6% ak/k, immediately initiate and continue boration at >30 gpm of 7000 ppm boron or equivalent until the required SHUTDOWN MARKIN is restored.
SURVEILLANCE REOUIREMENTS 4.1.1.1.1 The SHUTDOWN MARGIN shall be determined to be > 1.6% ak/k:
Within one hour after detection of an inoperable control rod (s) a.
and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter while the rod (s) is inoperable.
If the inoperable control rod is immovable or untrippable, the above required SHUTDOWN MARGIN shall be increased by an amount at least equal to the withdrawn worth of the immovable or untrippable control rod (s).
b.
When in MODES 1 or 2, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that control bank withdrawal is within the limits of l
Specification 3.1.3.5.
N When in MODE 2
, at least once during control rod withdrawal c.
and at least once per hour thereafter until the reactor is cri tical.
Prior to initial operation above 5% RATED THERMAL POWER after d.
each fuel loading, by consideration of the factors of e below, with the control banks at the maximum insertion limit of Specification 3.1.3.5.
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- See Special Test Exception 3.10.1 ith Keff > 1.0 "With Keff < 1.0 TROJAN-UNIT 1 3/4 1-1 Amendment No. 64 I
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il lf SUR7;;LLAT;LL f:E^d!RE.MENTS (Crih:2-M ii
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e.
When in MODES 3, 4, or 5, a least once per 24 nours oy consioera-l' tion of the following factors:
1.
Reactor coolant system baron concentration, 2.
Control rod position, 3.
Reactor coolant system average temperature, 4.
Fuel burnup based on gross thermal energy generation, 5.
Xenon concentration, and 6.
Samarium concentration.
4.1.1.1.2 The overall core reactivity balance shall be compared to predicted values to demonstrate agreement within + 1% ak/k at least once per 31 Effective Full Power Days (EFPD). This coiiiparision shall consider at least those factors stated in Specification 4.1.1.1.1.e, above. The predicted reactivity values shall be adjusted (normalized) to correspond to the actual core conditions prior to exceeding a fuel burnup of 60 Effective Full Power Days af ter each fuel loading.
J TROJAN-UNIT 1 3/4 1-2 Amendment No. 64 v
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CONTENTS OF THIS PAGE INTENTIONALLY DELETED 1
TROJAN-UNIT 1 3/4 1-3 Amendment No. 64
j i 5/4.1 RCACTI',*ITY C0:3.10. SYCTE:C ff li i s oncec l
1 3/4.1.1 SOP.ATION C0uvem 3/4.1.1.1 SHUTDOWN MAP.CIF A sufficient SHUTDnWW MARGIN ensures that 1) the reactor can be made subcritical from all operating conditions, 2) the reactivity transients associated with postulated accident conditions are controllable within acceptable limits, and 3) the reactor will be maintained sufficiently subcritical to preclude inacvertent criticality in the shutdown condition.
SHUTDOWN MARGIN requirements vary throughout core life as a function of fuel depletion, RCS boron concentration, and RCS Tavg. The mort restrictive condition occurs at EOL, with Tavg at no load operating temperature, and is associatec with a postulated steam line break accident and resulting uncontrolled RCS cooldown.
In the analysis of this accident, a minimum SHUTDOWN MARGIN of 1.6% ak/k it initially required to control the reactivity transient. Accordingly, the SdUTDOWN MARGIN requirement is based upon this limiting condition and is consistent with FSAR accident analysis assumptions. With Tavg less than 200*F, the most restrictive reactivity transients resulting from the postulated boron Dilution Accident are such that a 1.61 ak/k SHUT 00WN MARGIN is initially required.
3/4.1.1.3 BORON DILUTION A minimum flow rate of at least 3000 GPM provides adcquate mixing, prevents stratification and ensures that reactivity changes will be gradual during boron conctntration reductions in the Reactor Coolant System.
A flow rate of at litast 3000 GPM will circulate an equivalent Reactor Coolant l
System volume of 13,104 cubic feet in approximately 33 minutes.
The l
reactivity change rate associated with boron reductions will tr.erefore be within the capability for eperator recognition and control.
l 3/4.1.1.4 HODERATOR TEMPERATURE COEFFICIENT (MTC) l The limitations on MTC are provided to ensure that the assumptiens used in the accident and transient analyses remain valid through each fuel cycle. The surveillance requirement for measurement of the MTC at the beginning, middle, and near the end of each fuel cycle is adequate to l
confirm the MTC value since this coefficient changes slowly due l
l TROJAN-UNIT 1 B 3/4 1-1 Amendment No. 64
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