ML20132F023

Forwards Safety Evaluation Re Environ Qualification of Electric Equipment Important to Safety & Authorizes Interim Operation in dry-out Mode at Max 15% of Rated Power,Based on Listed Conditions,Until Technical Review Completed

ML20132F023
Person / Time
Site:	Fort Saint Vrain
Issue date:	07/19/1985
From:	Martin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:	Lee O PUBLIC SERVICE CO. OF COLORADO
Shared Package
ML20132F028	List: ML20132F023 ML20132F072
References
TAC-42527, TAC-54373, TAC-59787, NUDOCS 8508020165
Download: ML20132F023 (7)

Text

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JUL 191985 Docket:

50-267 Mr. O. R. Lee, Vice President Electric Production Public' Service Company of Colorado P.O. Box 840 Denver, Colorado 80201

Dear Mr. Lee:

We have reviewed the various submittals you have made in response to our October 16, 1984, " Preliminary Report Related to the Restart and Continued Operation of the Fort St. Vrain Nuclear Generating Station," and other submittals related to subjects which have required resolution prior to the resumption of operations at Ft. St. Vrain (FSV). We have provided the results of our reviews of the various areas of concern in a number of recently issued Safety Evaluations

( S E';). These safety evaluations contain the NRC findings on all issues associated with the above report.

In addition, we have approved some of your proposals for resolving some of our concerns which will require long-term actions. A listing of our SEs and approvals is contained in Enclosure 1, a listing of your various commitments is contained in Enclosure 2.

Our June 26, 1984, confirmatory action letter (CAL) confirmed your commitment that FSV would be maintained in a shutdown condition until the NRC authorized a different status. Our reviews have now progressed to such a point that we have determined that you have satisfied the commitments contained in our June 26, 1984, letter and have addressed the issues raised in the October 16, 1984, report. We find it acceptable, therefore, for FSV to be operated in a

" dry-out" mode to aid in the removal of moisture.

Such an operation would hold reactor power below a level at which boilout in the economizer-evaporator-superheater section of the steam generator would be achieved, but in no case greater than 15% Rated Thermal Power until such time as certain equipment qualification questions are resolved. Our evaluation of the acceptability of operating FSV in this mode is contained in the enclosed Safety Evaluation (Enclosure 3).

In addition, we have reviewed your proposed compensatory measures in the area of fire protection, contained in your letter dated July 11,1985,(P-85245)and find them to be an acceptable basis to allow interim operations until our technical review is completed. We have confirmed your commitments in the listing contained in Enclosure 2; a SE of our finding will be provided under separate cover.

In authorizing the restart and the operation of Fort St. Vrain at power levels not to exceed 15% power, understand that you have committed to the following actions:

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1.

Unless authorized by NRC to proceed to a higher power level, PSC will restrict plant power level to no greater than 15% power.

PSC shall notify the NRC of the completion of aging and equipment operability studies for equipment qualification under 10 CFR 50.49.

2.

PSC will continue to implement those items listed as complete and will resolve the longer range issues contained in Enclosure 2.

In doing so, the scope and schedule for resolution of these issues, that has been previously agreed to with the NRC staff, shall not be altered without prior agreement of the NRC staff.

If your understanding of these commitments is not the same as ours, please contact our office within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at (817) 860-8100.

Since these reporting requirements relate solely to the FSV, OMB clearance is not required under P.L.96-511.

Sincerely, C:1 c c-7,4 Robert D. Martin Regional Administrator

Enclosures:

1.

List of SEs and Approvals 2.

List of PSC Commitments 3.

SE Related to Environmental Qualifications cc:

Mr. D. W. Warembourg, Manager Nuclear Engineering Division Public Service Company of Colorado

. O. Box 840 P

Denver, Colorado 80201 Mr. David Alberstein, 14/159A GA Technologies, Inc.

P. O. Box 85608 San Diego, California 92138 (cont. on next page) i I

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p Public Service Company of Colorado Kelley, Stansfield & 0'Donnell Public Service Company Building 550 15th Street, Room 900 Denver, Colorado 80202 Chairman,' Board of_ County Comm.

of Weld County, Colorado Greeley, Colorado 80631 Regional Representative Radiation Programs Environmental Protection Agency 1860 Lincoln Street Denver, Colorado 80203 Mr. H. _ L. Brey, Manager Nuclear Licensing / Fuels Div.

Public Service Company of Colorado P. O. Box 840 Denver, Colorado 80201 J. W. Gahm, Manager, Nuclear Production Division Fort St. Vrain Nuclear Station 16805 WCR 191 Platteville, Colorado 80651 L. Singleton, Manager, Quality Assurance Division (same address)-

Colorado Radiation Control Program Director bec distrib. by RIV:

RSB Reading File Resident Inspector R. D. Martin, RA.

R. E. Ireland, RSB/ES P.. Wagner, RSB/ES

'R. Denise, DRS&P l

E. Haycraft, DRSP/LA RIV Official Reading File E. Jordan, IE E.

Butcher, ORB 3 CPB/NRR D. Eisenhut, D/DL G. Lainas, DL K. Heitner, ORB 3 J. Taylor, IE T. King, NRR l

l a

LIST OF SAFETY EVALUATION / APPROVALS ISSUED RELATED TO THE RESTART OF FORT ST. VRAIN Date Subject July 8, 1985 Prestressed Concrete Reactor Vessel Tendon Wire Corrosion Problem SE July 9, 1985 Liquid Effluent Release from the Reactor Building Sump.

July 10, 1985 Emergency Electrical Power Systems SE July 12, 1985 AssessmentReportSE(CRDM, Technical Specifications, and Management Controls)

July 12, 1985 CRDM Bearing SE letter I

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i PUBLIC SERVICE COMPANY OF COLORADO COMMITMENTS RELAltu TO THE OPERATION OF THE FORT ST. VRAIN NUCLEAR GENERATING STATION 1

1 I

Item Connitment Description / Requirement (Reference)

Schedule 1.

Implement a program to maintain CRDM temperature within acceptable limits.

Complete (P-185199 and P-85242)

(see Item 8) 1 2.

Provide an improved CRDM Surveillance and preventative maintenance program 6 months (P-85199andP-85242),whichincludesconsiderationofthenewbearingperformance after restart (P-85201).

3.

Implement a procedure to prevent overdriving of the CRDM.

(P-85040)

Complete (see 50P 12-01, Issue 15) 4.

Implement a procedure to require a reactor shutdown under conditions where CRDM Complete purge flow is lost or when high levels of moisture exists in the coolant.

(P-85040)

(see Item 8) 5.

Monitor CROM temperatures.

(P-85199 and P-85242)

Complete (see Item 8) i 6.

Provide status reports / progress reports on the Nuclear Performance Enhancement Approximately i

Program on a quarterly basis.

(P-85217) every 3 months 7.

Implement the Technical Specification (TS) Upgrade Program (P-85098) a.

Provide a final draft proposal of the Upgraded TSs for NRC comment.

(P-85243) 10/15/85 b.

Submit a license amendment to incorporate the Upgraded TSs.

(P-85243) 90 days after NRC comments on Item 7a c.

Implement the Upgraded TSs.

(P-85243)

Approximately the 4th Refueling Outage (License Amend-ment will define) i

Page 2 1

Item Commitment Description / Requirement (Reference)

Schedule 8.

Improve control rod and reserve shutdown reliability.

a.

Propose fechnical Specification changes.

(P-85242)

Complete b.

Implement proposed requirements through interim procedures.

(P-85242)

Complete i

Incorporate the proposed Technical Specifications in the Upgrade Program.

(See Item 7) c.

9.

Develop a plan to implement approved modifications to control moisture ingress Annually and submit annual reports on progress.

(P-85022 and P-85082)

Report Progress i

10.

Control moisture in CRDM purge system.

(P-85032) 4th Refueling Outage 1

11.

Perform environmental requalification testing of a CRDM assembly (P-85032) 12/30/85 including the temperature sensor epoxy.

(P-85195) 12.

Refine the " watt-meter" test for verification of control red full insertion 6 months or develop an alternative test.

(P-85040 and P-85199) after restart (see Item 2) 13.

Investigate a design change to provide a positive stop to prevent CRDM overtravel; 1/1/86 I

report results to the NRC.

(P-85003) l 14.

Conduct an integrated systems study to resolve control rod position indication, 6/30/86 maintenance and operability questions.

(P-85003) i 15.

Implement QA Procedure Review Program.

(P-85028) 7/1/86

)

16.

Liquid Effluent Releases from the Reactor Building Sump

a. Implement procedures to perform all effluent releases from the reactor building Complete sump in batch mode.

(P-85212) l

b. Investigate installing in-line, beta sensitive, effluent monitors and report In progress on progress.

(P-85212)

l Page 3 Item Commitment Description / Requirement (Reference)

Schedule

[

17.

PCRV Tendon Surveillance Requirements

a. Incorporate the revised Tendon Surveillance Program into the Technical (See Item 7)

Specifications.

(P-85199)

b. Implement the revised program through the use of interim procedures.

(P-85199)

Complete

c. Provide the results of the revised program to the NRC Approximately-Every 6 months i

18.

Propose modifications in the Emergency Diesel Generator circuit breakers' control 9/15/85 circuitry to resolve the independence problem.

(P-85208) 19.

Fire Protection Interim Requirements

a. Implement the special (and interim) repair and operating procedures.

Complete l

(P-85113 and P-85245)

b. Implement a fire watch program.

(P-85245)

Complete 20.

Complete the CRDM bearing performance testing and incorporate results Report on into the improved CRDM surveillance and preventative maintenance program progress I

identified in Item 2 above.

(P-85201)-

quarterly i

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