ML20141P035

Supports Util 860311 Request for Emergency Amend to Tech Spec 3.2.A,changing Main Steam Line High Flow Isolation Setpoint Limit to 150% Rated Steam Flow.Waiver in Effect Until 860317

ML20141P035
Person / Time
Site:	Cooper
Issue date:	03/13/1986
From:	Muller D Office of Nuclear Reactor Regulation
To:	Pilant J NEBRASKA PUBLIC POWER DISTRICT
References
NUDOCS 8603180462
Download: ML20141P035 (4)

Text

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. ~-w Docket No.: 50-298 Mr. J. M. Pilant, Technical Staff Manager Nuclear Fower Group W I3 5 Nebraska Public Power District Post Office Box 499 Colurrbus, Nebraska 68601

SUBJECT:

EMERGENCY TECHNICAL SPECIFICATION CHANGE f%IN STEN! LItiE HIGH FLOW ISOLATION SETPOINT Re: Cooper Nu::) ear Station Your letter dated March 11, 1986 requests an errergency amendment to Technical Specification 3.2.A. The proposed ar.1endment would change the niain steam line high flow isolation setpoint limit from 140% rated steat flow to 150% rated steam flow as indicated in the enclosures.

We have reviewed your evaluation (letter frcm W. Yee, General Electric, to G. Horn (NPPC) dated itarch 6,1986) and find it acceptable. This letter will confirn the verbal granting of a temporary walver of compliance as recorded by the NRC Operations Center on March 10, 1986. This waiver of compliance will be in effect until March 17, 1986.

Sincerely, Ov90ndMlW Duld R.W Daniel R. Ful le~r, D. ..irector UWR Project Directorate #2 Divisten of BWR Licensing

Enclosures:

DISTRIBUTION: ,

Proposed anended Cooper Technical 4NA Specifications pages 50 and 84 hRC POR Local POR cc w/ enclosure RBernero See next page SNorris WLong GELD LHarmon EJordan UGrines JPartlow D

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Mr. J. M. Pilant Nebraska PLblic Power District Cooper Nuclear Station ec:

Mr. G. D. Watson . General Counsel Nebraska Public Power District P. O. Box 4999 Columbus, Nebraska 69601 fir. Arthur C. Gehr, Attorney Snell & Wilmer 3100 Valley Center Phoenix, Arizona 85073 Cooper Nuclear Station ATTN: Mr. Paul Thomason, Division Manager of Nuclear Operations P. O. Box 98 Grewnville, Nebraska 68321 Director f etraska Department of Environmental

. Control P. O. Box 94877

. State House Station Lincoln, Nebraska 63509 Mr. William Siebert, Commissioner Nemaha County Board of Commissioners Netaha County Courthouse Auburn, Nebraska (8305 Resident Inspector U.S. Nuclear Regulatory Consission F. O. Box 218 Brovnville, Nebraska 68321 P.egional Administrator, Region IV

. U.S. Nuclear Pegulatory Cannission 611 Ryan Plaza Drive, Suita 1000 Arlington, Texas 76011 H. Ellis Simmons, Director Division of Padiological Health Department of Health

! 301 Centennial Mall, South

! P. O. Box 95007

! tincoln, Nebraska 68509

CODFER WDCLEAR STATION ej TABLE 3.2.A (Fase 1) pf FanskeY CWTAIEBENT AB REACTOR TESSEL ISCEATIOh JSTE5BGBTATICE h

% O k

v]}, Nimi=== Neuber Action Rege meu g Imetrusset of Operable e __, x..te Courseest Oper ility w lastresset I.B. No. Settien Limit Per Trip system (1)

N is Not Assured 2)I $

• Mate Steam Lies Eigh E19-35-251. A.B.C.43 $ 3 Timee Full Famer 2 A or B Bad.

~ Besetor low Meter Eavel M 1-L15-let. A.B.C 85 1+12.5" Indleated inwel 2(4) A or a mesetor ime les Ester BRI-LIS-57 & & B #2 1-37" ladiented invel 2 A er B Imwel NBI-LIS-58 A & B #2 l

j o

Beseter low Ime Law Enter NET-LIS-57 A & B #1 1-145.5" Indicated Level 2 A er B Insel NBI-L15-58 A & B #1 Main Steen 11ee leek 15-T5-128. A.B.C.43 < 200*F

'~ 2(6) 3

• Detectice 122. 123. 124. 143, 144 E

- . . . . - . 145, 146. 147. 148. 149.. . ..-. . . -- - - ..

. 150  !

unie seems ties aish us4Fis-116 A.B.C.&B i 1501 of Eated Steau 2(3) 3 l Flow 117. 118. 119 Flow Meie Steam Lien ime 15-PS-134. A.B.C &D 1 825 pois 2(5) 3 6f

$i ES$ Dryuell Pressere PC-PS-12. A.B.C 8D 1 2 pois 2(4) A or B Ei$ Beactor Pressure RR-PS-128 A & B 3 75 peig 1 3 Nois r % low Tecome MS-PS-103. A.B.C,6D 1 7" Eg (7) 2 A er B g,

Soester Meter Cleomey RIEW-dFIS-170 A & 5 1 2001 of System Flow 1 C System Eigh Fles 0

• e b l

03/11/86 ' 84:57 ffPD COLLP1 BUS GO NO.009 009 3.2 RASF,8 :

(Cont'd)

I and the guidelines of 10CFR100 will not be exceeded. For large breaks up..

to the complete circumferential break of a 28-inch recirculation line and I with the trip setting given above, CSC8 initiation and primary systen l 1 solution are initiated in time to meet the above criteria. Reference Paragraph VI.5.3.1 USAR.

The high drywell pressure instrumentation is a diverse signal for sal-tunctions to the water level instrumentation and in addition to initiating CSC5, it causes isolation of Group 2 and 6 isolation valves. For the breaks discussed above, this instrumentation will generally initiate CgC5 operation before the low-low-low water level instrumentation; thus the results given above are applicable here also. The water level instrumen-tation initiates protection for the full spectrum of loss-of-coolant accidents and causes isolation of all isolation valves except Groups 4 and 5.

Venturis are provided in the main steam lines as a means of measuring steam flow and also limiting the loss of mass inventory from the vessel during a steam line break accident. The primary function of the instru-mentation is to detect a break in the main eteen line. For the worst case of accident, main steam line break outside the drywell, a trip setting of 150% of rated steam flow in conjunction with the flow limiters and main steam line valve closure limits the mass inventory low. such j that fuel is not uncovered, fuel clad temperatures peak at.approximately 1000*F and release of radioactivity to the environs is below 10CFR100 guidelines. Reference section 11V.6.5 USAR.

I Temperature monitoring instrumentation'io provided in the main steam tunnel and along the steam line in the turbine building to detect leaks in these areas. Trips are provided on,this instrumentation and When exceeded, cause closure of teclation valves. See Spec. 3.7 for Yalve Group. The setting to 200*F for the main steam laak detection system.

For large breaks, the high steam flow instrumentation is a backup to the temp. instrumentation.

Righ radiation monitors in the main steam tunnel have been provided to detect grose fuel failure as in the control rod drop accident. With the established setting of 3 times normal background, and main steam line isolation valve closure, fission product release is limited so that 10CFR100 guidelines are not exceeded for this accident. Reference see-tion XIV.6.2 USAR.  ;

Pressure instrumentation is provided to close the main steam isolation valves in RUN Mode when the main steam line pressure drope below Speci-fication 2.1.A.6. The Beactor Pressure Vessel thermal transient due to an inadvertent opening of the turbine bypass valves when not in the RUN Mode to less severs than the loss of feedwater analysed in section XIV.5 l ef the USAR, therefore, closure of the Main steam Isolation valves for l thermal transient protection when not in RUN sode is not required.

The Esseter Water Cleanup System high flow and temperature instrumentation are arranged similar to that for the E!CI. The trip settings are such that core uncovery is prevented and fission product release is within limits.

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