ML19345H190
| ML19345H190 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 04/16/1981 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19345H187 | List: |
| References | |
| NUDOCS 8105010189 | |
| Download: ML19345H190 (7) | |
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UNITED STATES 5
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'e NUCLEAR REGULATORY COMMISSION O
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PORTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE, OREGON PACIFIC POWER AND LIGHT COMPANY DOCKET NO. 50-344 TROJAN NUCLEAR PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 58 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 December 28, 1979, as supplemented June 19, 1980 and March 23, 1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set fortn 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 (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 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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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. HPF-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. 58, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications, except as noted in paragraphs 2.C.(10) through 2.C.(12) below.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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L A-Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: April 16, 1981 t
ATTACHMENT TO LICENSE AMENDMENT AFENDRENT NO. 53 TO FACILITY OPERATING LICENSE NO. NPF-1 DOCKET NO. 50-344 Revise Appendix A as follows:
Remove Paces Insert Paoes 3/4 1-15 3/4 1-15 3/4 8-4 3/4 8-4 8 3/4 1-3 B 3/4 1-3 B 3/4 1-4 8 3/4 1-4
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REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCES - SHUTDOWN LIMITING CONDITIONS FOR OPERATION 3.1.2.7 As a minimum, one of the following borated water sources shall be OPERABLE:
a.
One boric acid storage tank with:
1.
A minimum contained volume of 12,600 gallons.
l 2.
Between 7,000 and 7,700 ppm of baron, and 3.
A minimtm solution temperature of 65*F.
b.
The refueling water storage tank with:
1.
A minimum contained volume of 102,000 gallons, 2.
Between 2,000 and 2,500 ppm of boron, and 3.
A minimum solution temperature of 37'F.
APPLICABILITY: MODES 5 and 6.
ACTION:
With no borated water sources OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes until at least one barated water source is restored to OPERABLE status.
SURVEILLANCE REOUIREMENTS 4.I.2.7 The above-required borated water source shall be demonstrated OPERABLE:
a.
At least once per 7 days by:
1.
Verifying the baron concentration of the water, 2
Verifying the water level of the tank, and 3.
Verifying the boric acid storage tank solution temperature wnen it is the source of borated water and the outside amoient air temperature is <37'F.
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TRCJ AN-UNIT 1 3/4 1-15 Amendment No. 58
t ELECTRICAL DOWER SYSTEMS SUR'.E:LLAHCE RECUIREMENTS (Continued) d) Verifying that on diesel generator trip, the loads are shed from :ne emergency busses and tne diesel re-starts on the auto-star: signal, I
the emergency busses are energized with per-manently ccnnected icads, the aut:-cennected emergency loads are energi:ed tnrcugn the load secuencer and :ne ciesal ccerates fer > 5 minutes
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wnile its genera:cr is leaded wi n -he emergency loads.
4 Verifying the diesel genera:cr se cperatas > 50 minutes wnile loaded to 3 3364 kw.
5.
Verifying :na: r.e au o-cennected leads to each diesel genera:ce uni: do nc: exceed :ne 2000 hcur rating of 4752 kw.
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- c. sA ieast cnce per 15 mcnths by verifying tha; each fuel trans-fer pump transfers fuel from its associated fuel storage tank to the day tank of each diesel via the installed cross connection i
lines.
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-lTECJAN-UNIT 1 3/1 3 4 Amendment No. 57, 58
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P00RORIGINA!.
REACTIVITY CONTROL SYSTEMS BASES 3/4.1.2 00 RATION SYSTEMS (Continued)
With the RCS temperature below 200*F, one injection system is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity change in the event the single injection system becomes inoperable.
The boron inventory in the RWST or BAT is sufficient (a) to compen-sate for an inadvertent positive reactivity addition to the Reactor Coolant System of approximately 1 percent ak/k while in MODE 5 at 200*F; and (b) to maintain a constant RCS reactivity while the temperature is decreased from 200*F to 80*F.
In MODE 6, the BAT inventory is sufficient to increase ths boron concentration to compensate for an inadvertent positive reactivity addition of appoximately 1 percent ak/k while in the refueling mode. These conditions require 8494 usable gallons of 7000-ppm barated water from the baric acid storage tanks or 23,432 usable gallons of 2000-ppm barated water from the refueling water storage tank.
The required boric acid storage '.ank volume of 8494 gallons has been increased to a value greater than the minimum level. indicating range (4050 gallons), to 12,544 gallons.(rounded to 12,600 gallons). The i
required RWST volume of 23,432 gallons must be increased to account for l
nonusable volume due to tank geometry, letdown and vortexing considerations l
(78,000 gallons), to 101,432 gallons (rounded to 102,000 gallons).
I 3/4.1.3 MOVABLE CONTROL ASSEMBLIES The specifications of this section ensure that (1) acceptable power distribution limits are mantained, (2) the minimum SHUTDOWN MARGIN is maintained, and (3) limit the potential effects of a red ejection accident.
CPERABILITY of the control rod position indicators is requirec to determine control rod positions and thereby ensure compliance with the control rod alignment and insertion limits.
The ACTION statements which permit ifmited variations from the
- basic recuirements are accompanied by additional restrictions which ensure tnat the original criteria are met. Misaldgnment of a rod requires measurement of peaking factors or a restriction of THERMAL POWER; eitner of these j
restrictions provides assurance of fuel rod integrity during continued
- peration. The reactivi y wceth of a misaligned rod is limited for -ne
-enainder of the fuel cycle to prevent exceeding the assumptions used in r.e accident analysis for a red ejection accident.
~he maximum rod droo time restriction is consistent with the assumed
- d crop time used in :ne accident analyses.
Measurement w' ch Taye >55F ar.c with all reactor coolant pumps cperating ensures that the measured cr:0 times will be representative of insertion times experienced during a reactor tris at cperating conditions.
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'ROJAN-UNIT 1 B 3/4 1-3 Amendment he. 58
REACTIVITY CONTROL SYSTEMS BASES 3/4.1.3 MOVABLE CONTROL ASSEMBLIES (Continued:
Control red positions and CPERABILITY of tne rod position indicators are required to be verf +ied 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 /> witn more frecuent verifications requirea if an automatic monitoring channel is inoperaole. These verification frequencies are acequate for assuring tnat tne applicaole LCO's are satisfiec.
The restriction prohibiting part length rod insertion ensures tnat aaverse power snapes and rapid local power changes wnicn may erfect DNB considerations ao not occur as a result of part length red insertion curing operation.
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l TROJAN-UNIT 1 B 3/4 1-4 Amendment tio. 58 l
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