ML20214W436
| ML20214W436 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 12/05/1986 |
| From: | Heitner K Office of Nuclear Reactor Regulation |
| To: | Robert Williams PUBLIC SERVICE CO. OF COLORADO |
| Shared Package | |
| ML20214W440 | List: |
| References | |
| CON-FIN-A-9351 TAC-52634, NUDOCS 8612100225 | |
| Download: ML20214W436 (5) | |
Text
h, -. - *.
t g
UNITED STATES
[
g NUCLEAR REGULATORY COMMISSION 5
- j WASHINGTON, D C. 20555
/
December 5, 1986 g
Docket No. 50-267 Mr. R. O. Williams, Jr.
Vice President, Nuclear Operations Public Service Company of Colorado Post Office Box 840 Denver, Colorado 80201-0840
Dear Mr. Williams:
SUBJECT:
FORT ST. VRAIN TECHNICAL SPECIFICATION LC0 4.1.9 We are continuing our review of your submittal dated July 9,1986 (P-86451) regarding Limiting Condition for Operation (LCO) 4.1.9.
The revision of this Technical Specification has been under consideration by the staff since late 1983. Durin Laboratory (ORNL)g this time, the staff contracted with Dak Ridge National to review certain aspects of your proposed changes.
ORNL has prepared a Technical Evaluation Report (TER) concerning their review. This TER has been reviewed by the staff, and is enclosed for your infomation.
However, certain aspects of your current proposal for LC0 4.1.9, not addressed by the TER, remain under review. gpecifically,thestaffremainsconcerned about your proposed use of the 760 F bulk core temperature concept. The concern is that potentially all decay heat removal paths from the core would beinterruptedbagedsolelyonthecalculationthatthebulkcoretemperature was less than 760 F.
During this period when heat removal paths were inter-rupted, there could be no monitoring of core temperatures.
The staff believes that a more conservative approach would be to maintain at least one decay heat removal path operating, and a second path operabh except for a specified period where operation was not possible (i.e.,
circulator removal, etc.). The staff also stated that their preference was for the allowed outage time to be explicitly determined from curves in the Technical Specification. These curves would give the allowed outage time based on appropriate input parameters. The specification should also con-tain specific upper limits on the time period when forced circulation was interrupted.
This issue was discussed on October 30, 1986, at the meeting on the Technical Specification Upgrade Program (TSUP).
Your staff made the following points in response to the staff's concerns:
- One loop of the liner cooling system (LCS) is always operating under the provisions of LC0 4.2.13 and LC0 4.2.15.
(This is an implied requirement, and not explicit in the LCO's.) Corresponding LCOs were included in the TSUP.
- Operation of this loop could be backed up by the firewater system to provide a second operable path.
861.210022S 861205 DR ADOCK 0500 7
i Decemb:r 5,1986 Mr. R. O. Williams, Jr. - Historical data existed to validate the core heatup model used for these calculations.
- A specific upper time limit when forced circulation was interrupted was feasible, so long as it accounted for worst case maintenance operations, such as circulator removal.
Based on these discussions, we believe a basis for an acceptable proposal for LCO 4.1.9 exists.
Specific elements of that proposal include the following:
- An explicit commitment by Public Service Company of Colorado (PSC) to maintain one loop of the LCS in operation under the provisions of LC0 4.2.13 and LC0 4.2.15.
- A commitment by PSC to back up this operable loop with the firewater system when this is the only decay heat removal path.
- Revision of the proposed Technical Specification to include the curves for determining the allowed outage time and the inclusion of a specific outage time limit.
We request that you provide a new submittal that addresses the staff concerns as outlined above.
Please provide the required information within 45 days of the date of this letter.
The information requested in this letter affects fewer than 10 respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely.
Original signed b_y Kenneth L. Heitner, Project Manager Standardization and Special Projects Directorate Division of PWR Licensing-B Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/ enclosure:
See next page DISTRIBUTION:
,qDocket. File w Olynch NRC PDR^ ^
HBerkow Local PDR GLPlumlee, PBF0 PBSS Reading ELuntz, PARS PNoonan RIreland, R-IV KHeitner CThomas, PARS
- SEE PREVIOUS CONCURRENCE SHEET H$gh PB R-IV*
- PBSS*
PBSS*
PBSS*
eytow RIreland CThomas PNoonan KHeitner:ac 0 Lynch 11/20/86 12/02/86 12/02/86 12/ 7 /86 12/04/86 12/04/86
Mr. P. O. rIlliams, Jr. - Historical data existed to validate the core heatup model used for these calculations.
- A specific upper time limit when forced circulation was interrupted was feasible, so long as it accounted for worst case maintenance operations, such as circulator removal.
Based on these discussions, we believe a basis for an acceptable proposal for LC0 4.1.9 exists.
Specific elements of that proposal include the following:
- An explicit connitment by Public Service Company of Colorado (PSC) to maintain one loop of the LCS in operation under the provisions of LC0 4.2.13 and LC0 4.2.15.
- A commitment by PSC to back up this operable loop with the firewater system when this is the only decay heat removal path.
- Revision of the proposed Technical Specification to include the curves for determining the allowed outage time and a inclusion of a specific outage time limit.
We request that you provide a new submittal that addresses the staff concerns as outlined above. Plt.ase provide the required information within 45 days of the date of this letter.
The information requested in this letter affects fewer than 10 respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely, Kenneth L. Heitner, Project Manager Standardization and Special Projects Directorate Division of PWR Licensing-B Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/ enclosure:
See next page DISTRIBUTION:
Docket File 0 Lynch NRC PDR HBerkow Local PDR GLPlumlee, PBF0 PBSS Reading ELuntz, PARS PNoonan Rlreland, R-IV KHeitner CThomas, PA
{#
PBSS N P.
Ph R-IVEL PA Sp( p onan KHeitner:ac 0 Lynch HBe?kow RIreland y
1/$/86 17/Z./86 11/V/86 11/f/86 12/t/86 86
Mr. R. O. Williams, Jr..
- Historical data existed to validate the core heatup model used for these calculations.
- A specific upper time limit when forced circulation was interrupted was feasible, so long as it acccunted for worst case maintenance operations, such as circulator removal.
Based on these discussions, we believe a basis for an acceptable proposal for LCO 4.1.9 exists.
Specific elements of that proposal include the following:
- An explicit commitment by Public Service Company of Colorado (PSC) to maintain one loop of the LCS in operation under the provisions of LC0 4.2.13 and LC0 4.2.15.
- A commitment by PSC to back up this operable loop with the firewater system when this is the only decay heat removal path.
- Revision of the proposed Technical Specification to include the curves for detennining the allowed outage time and the inclusion of a specific i
outage time limit.
We request that you provide a new submittal that addresses the staff concerns as outlined above.
Please provide the required information within 45 days of the date of this letter.
The information requested in this letter affects fewer than 10 respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely, o
x Kenneth L. Heitner, Project Manager Standardization and Special Projects Directorate Division of PWR Licensing-B i
Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/ enclosure:
See next page
Mr. R. O. Williams Public Service Company of Colorado Fort St. Vrain cc:
Mr. D. W. Warembourg, Manager Albert J. Hazle, Director Nuclear Engineering Division Radiation Control Division Public Service Company Department of Health of Colorado 4210 East lith Avenue P. O. Box 840 Denver, Colorado 80220 Denver, Colorado 80201 Mr. David Alberstein, 14/159A Mr. J. W. Gahm, Manager GA Technologies, Inc.
Nuclear Production Division Post Office Box 85608 Public Service Company of Colorado San Diego, California 92138 16805 Weld County Road 19-1/2 Platteville, Colorado 80651 Mr. H. L. Brey, Manager Nuclear Licensing and Fuel Division Mr. P. F. Tomlinson, Manager Public Service Company of Colorado Quality Assurance Division P. O. Box 840 Public Service Company of Colorado Denver, Colorado-80201 16805 Weld County Road 19-1/2 Platteville, Colorado 80651 Senior Resident Inspector U.S. Nuclear Regulatory Commission Mr. R. F. Walker P. 0. Box 840 Public Service Company of Colorado Platteville, Colorado 80651 Post Office Box 840 Denver, Colorado 92138 Kelley, Stansfield & 0'Donnell Public Service Company Building Commitment Control Program Room 900 Coordinator 550 15th Street Public Service Company of Colorado Denver, Colorado 80202 2420 W. 26th Ave. Suite 100-D Denver, Colorado 80211 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Chairman, Board of County Commissioners of Weld County, Colorado Greeley, Colorado 80631 Regional Representative Radiation Programs Environmental Protection Agency 1 Denver Place 999 18th Street, Suite 1300 Denver, Colorado 80202-2413
_ - _