ML20141P177

From kanterella
Jump to navigation Jump to search

Summary of 860130 Meeting W/Util,Inel,Tenera & Sargent & Lundy Re Equipment Qualification (EQ) Program.List of Attendees,Test Profiles & Review of Sample EQ Package Encl
ML20141P177
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 03/14/1986
From: Heitner K
Office of Nuclear Reactor Regulation
To: Lynch O
Office of Nuclear Reactor Regulation
Shared Package
ML20141P178 List:
References
TAC-42527, NUDOCS 8603190116
Download: ML20141P177 (6)


Text

.-

  • gan 1 o UNITED STATES g

& n NUCLEAR REGULATORY COMMISSION '

o,  :; ,y WASHINGTON, D. C. 20555 k*****,o/ March 14, 1986 Docket No. 50-267 MEMORANDUM FOR: Oliver D. T. Lynch, Jr., Section Leader Standardization & Special Projects Directorate Division of PWR Licensing-B FROM: Kenneth Heitner, Project Manager Standardization & Special Projects Directorate Division of PWR Licensing-B I

SUBJECT:

SUMMARY

OF MEETING WITH PUBLIC SERVICE COMPANY OF COLORADO (PSC) ON FORT ST. VRAIN (FSV) EQUIPMENT QUALIFICATION (EQ)

PROGRAM, JANUARY 30, 1986 The purpose of this meeting was for PSC to discuss with the staff certain aspects of PSC's EQ program for FSV. Attendees at this meeting are listed in Enclosure 1.

Several issues concerning the FSV EQ program were discussed. These are summarized as follows:

1. Test Profiles - As part of FSV's equipment qualification program, a number of FSV equipment items were originally tested for 30 minutes at high temperatures. A typical test profile and the envelope of plant accident profiles is shown in Enclosure 2. PSC indicated for certain equipment items, that they would " extend" the equipment test profile to the 30 day time limit by analytical methods. The staff commented that this approach should not be used extensively because the methodology could yield non-conservative results.
2. Review of Sample E0 Package - The licensee presented a sample section from an EQ file currently being compiled. This is shown in Enclosure
3. The staff commented that service life and post accident margins could be added in a more simplified approach than proposed by PSC.

The staff also stated that all supporting analysis reports should be available at the reactor site.

3. EQ Submittal - The staff recommended that PSC review the submittal made for Point Beach Unit Nos. I and 2 as a basis for preparing their own EQ submittal. ,
4. EQ Schedule - PSC stated their current schedule is to have the FSV EQ program completed by May 1, 1986.
5. RG 1.97 Schedule - The staff noted that PSC is comitted to implement RG 1.97 requirements by the 4th refueling. This is currently projected for 1987.

8603190116 860314 PDR ADOCK0500g7

6. Compliance with General Design Criteria (GDC) 11. The staff noted that the requirement for the operators to take local manual actions to restore forced circulation cooling after an accident did not appear to be consistent with the original FSAR statements on GDC 11. The staff stated that they would make this concern a subject of separate correspondence.

At the conclusion of the meeting, it was decided that a plant visit and subsequent meeting to further discuss EQ would be set up for mid-February.

\

/r b[

Kenneth Heitner, Project Manager f- Standardization & Special

  • Projects Directorate Division of PWR Licensing-B

Enclosures:

As stated cc w/ enclosures:

See next page

. . March 14, 1986_

50- 2-G i 6. Compliance with General Design Criteria (GDC) 11. The staff noted that

^

the requirement for the operators to take local manual actions to restore forced circulation cooling after an accident did not appear to be i consistent with the original FSAR statements on GDC 11. The staff stated that they would make this concern a subject of separate correspondence.

At the conclusion of the meeting, it was decided that a plant visit and

, subsequent meeting to further discuss EQ would be set up for mid-February, i

i original signed by Charles S. Hinson for Kenneth Heitner, Project Manager Standardization & Special Projects Directorate Division of PWR Licensing-B

Enclosures:

As stated cc w/ enclosures:

See next page DISTRIBUTION:

Docket-File NRC PDR q Local PDR l i SSPD Reading l 4

HBerkow PNoonan  ;

0 Lynch .

KHeitner '

OELD EJordan BGrimes ACRS (10)

NRC Participants cc: Licensee and Plant Service List

.D B:SSPD DPWRL D DPWRL:B D

/P n KHeitner:ac Olynch 03/D/86 03////86 03/d/86

4

. Mr. R. F. Walker 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

'E Platteville, Colorado 80651

.P Mr. H. L. Brey, Manager Nuclear Licensing and Fuel Division Mr. L. W. Singleton, Manager Public Service Company of Colorado Quality Assurance Division P. O. Box 840 Fort St. Vrain Nuclear Station Denver, Colorado 80201 16805 Weld County Road 19-1/2 Platteville, Colorado 80651 Senior Resident Inspector U.S. Nuclear Regulatory Commission P. 0. Box 640 Platteville, Colorado 80651 Kelley, Stansfield & 0'Donnell Public Service Company Building Room 900 550 15th Street Denver, Colorado 80202 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Office of Executive Director for Operations 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 ,

1800 Lincoln Street Denver, Colorado 80203

f Enclosure 1 ATTENDEES AT MEETING NRC-PSC January 30, 1986 Name Organization M. J. Spisak S&L G. T. Hubbard IE/NRC J. M Fehringer INEL

). Max Yost INEL Paul Shemanski NRC/PWR-B A. S. Masciantonio NRC/NRR/PWR-A Sam Marquez PSC James Selan PSC Mike Niehoff PSC Ken Heitner NRC/NRR/PWR-B i

Rob Burg Tenera j

I i

l 1

I I

j l

g.. .r' ENCLOSURE 2 PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION 600 -

l l

l >

l l

500 -

7

/ * "*\  ;

'\ l

/ -

\

l l

[

400 -

, '\ TYPICAL TEST PROFILE l y I 1

Lu I g

H 300 -

f m ._._._._._._.s, N-i I

et j

.f ss i e . i 200

/ '

h 7 ,

PLANT ACCIDENT PROFLE 100 j

l I

I

%l ENVELOPING CURVE -! - MATERIALS ANALYSIS l

I I I I I I I I I I I I 2s 4s 10s im 2m 10m 30m lh 3h Id 10d 30d TIME t

.