ML20236D154
| ML20236D154 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 07/20/1987 |
| From: | Heitner K Office of Nuclear Reactor Regulation |
| To: | Robert Williams PUBLIC SERVICE CO. OF COLORADO |
| References | |
| TAC-65241, NUDOCS 8707300333 | |
| Download: ML20236D154 (3) | |
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. July 20,~1987 r
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- Docket'No.50-267' Mr. R.' 0. Williams,' Jr.
Vice Presidentc Nuclear 0perati.ons'
- Public Service Company of-Colorado P.'O. Box 840-DenvernColorado; 80201-0840 o
Dear Mr.l Williams:
?
SUBJECT:
. TECHNICAL SPECIFICATION 3/4.1.7,~ REACTIVITY'C'ANGE WITH TEMPERATURE d
-(TAC NO. 65241)'
'We' are. review'ng =your proposed change to interim Technical Specification -
'3/4.1.7, Reactivity Change with Temperature,-submitted by letter dated' April 8,
.1987 (P-87056).
-In' order to complete ~this review,.we request that you provide t
lthe additional-information requested in the enclosure to this letter..We re-i
' quest this information_be provided'within.60 days of the date of.this letter.
The information requested in this letter affects fewer than 10 respondents;:
therefore,- 0MB clearance is not required under P.L '96-511.
' Sincerely, Is/
L Kenneth L.'Heitner, Project Manager Project Directorate -'IV Division lof Reactor Projects - III, IV and V and'Special Projects Office of Nuclear Reactor. Regulation
Enclosure:
As Stated
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' Mr.; D ! W.' Warembourg, Manager Albert J. Hazle, Director.:
'y Nuclear. Engineering Division
" Radiation Control Division-p;,
Public Service. Company-Department'of Health'
<j of Colorado 4210. East' lith Avenue
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-P.iO.-Box 840!.
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. Denver,1 Colorado:'80201'.
Denver, Colorado 1 80220 1
'Mr. David:Alberstein, 14/159A.
Mr.:RL0.1Williaos,ActingManager;
- GA Technologies, Inc.
Nuclear Production Division l
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' Post Office Box.85608.
Public~ Service-Companyof.ColoradoL San Diego; California 92138' 16805. Weld County Road 19-1/23 F.1 Platteville,ColoradoS80651-u Mr. - H.
L.- 1 Brey,' Manager E
Nuclear Licensing and Fuel Division Mr. P. F. Toelinson,. Manager tPublic Service Company of. Colorado-
- Quality-Assurance Division
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P. 0. Box;840 E
. Denver, Colorado.'80201.
Public Service Company of Colorado 16805 Weld County Road 19-1/2<
l Platteville, Colorado 1 80651
' Senior Resident' Inspector'..
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iU.St Nuclear Re'gulatory Commission Mr.. R. F. Walker P.j0.80x: 840 Public Service Company of Colorado Platteville, Colorado' 80651 Post' Office Box 840^. '
Kelley,iStansfield &l0'Donnell Public Service' Company' Building Commitment control Program:
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- Room 900;
. Coordinator-550'15th' Street Public Service Company of Colorado i'
Denver,: Colorado '80202 2420 W. 26th Ave.L Suite 100-D
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1 Denver, Colorado' 80211 y
Regional' Administrator,' Region IV LU.S. Nuclear! Regulatory Commission.
-611 Ryan Plaza. Drive, Suite 1000' t Arlington,. Texas '76011 Chairman, Board of County' Commissioners of Weld County, Colorado
. Greeley, Colorado -80631 s.
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RegionaliRepresentative
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EnvironmentalaProtection Agency
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7 ENCLOSURE REQUESTFORADDITIONALINFdRMATION i
FORT ST. VRAIN NUCLEAR GENERATING STATION DOCKET NO. 50-267 Three questions have been developed from the submittal dated April 8, 1987 (P-87056) containin0 a proposed Technical _ Specifications change for Fort St.
Vrain (FSV).
Public Service' Company of Colorado should answer these-questions i
before an evaluation can be made.
i 1.
Has the prev'ous Technical Specification value for the maxium temperature defect (.056 delta k) ever been produced by a measurement result; i.e.,
has a mease; ament result ever caused a plant shutdown?
2.
' From Attachtnent Three, it appears that the calculated worth for the re-serve shutdown system (RSS) of.13 delta k does not allow-for the highest i
worth rod being stuck or in the case of FSV the RSS poison balls failing i
to drop in the most worthy channt!. What is the basis for not taking an allowance for the maximum worth unit being inoperable?
Is the analysis consistant_with Section 3.2.3 of the January 20, 1972 Safety Evaluation by the USAEC?
I 3.
The calculated excess reactivity for the equilibrium core with a core.
average temperature of 220 degrees F, Xe-135 decayed, Sm-149 buildup, and two-week Pa-233 decay is.102 delta k.
Are these the same conditions as' assumed in the calculation of the RSS reactivity worth'(.13 delta k)?
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