ML20236H279
| ML20236H279 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 10/29/1987 |
| From: | Robert Williams PUBLIC SERVICE CO. OF COLORADO |
| To: | Calvo J NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM), Office of Nuclear Reactor Regulation |
| References | |
| GL-83-28, P-87389, TAC-52840, NUDOCS 8711040052 | |
| Download: ML20236H279 (4) | |
Text
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P.O. Box 840
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.0ctober 29,.1987 Fort St. Vrain t n.O. WILLIAMS, JR.
Unit No. 1 vicE PRESIDENT NUCLEAR OPERATIONS P-87.389, s..
i U. S. Nuclear Regulatory Commission ATTN:. Document Control Desk Washington, D.C.
20555
' Attention: Mr. ' Jose A. 'Calvo-I Director, Project Directorate IV 4
Docket No. 50-267 i
SUBJECT:
Additional Information en Generic Letter 83-28 i
REFERENCE:
- 1. NRC Letter, Heitner to Williams dated 8/31/871 (G-87298)
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- 2. NRC Letter, Heitner to Williams dated 3/20/87 (G-87092)
Dear Mr. Calvo:
Attached is~ a description of the program in place at Fort St. Vrain
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and enhancements that are. underway to ensure that vendor interface is established and maintained'or that compensating measures exist where
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a formal vendor interface.cannot be practicably established for
. sa f ety - related components. This is in response to your requests for a
information in References (1) and (2).
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If you have any questions, please contact Mr. M. H. Holmes at (303) 480-6960.
j Sincerely, R.o AA~ b)'
k R. O. Williams, Jr.
Vice President, Nuclear Operations i
R0W:FJN/skd Attachment
'8711040052 871029 hD PDR ADOCK 05000267 p
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October 29, 1987
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l cc: Regional Administrator, Region IV ATTN: Mr. T. F. Westerman, Chief Projects Section B
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s Mr. Robert Farrell Senior Resident Inspector Fort St. Vrain
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ATTACHMENT 1
1 PUBLIC SERVICE COMPANY OF COLORADO RESPONSE 1
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' Public Service Company of Colorado (PSC) has, within:the past' year,.
completed a program to rewrite and. initially. generate maintenance procedures in an overall effort to improve the 'conductiof maintenance.
--at' Fort St; Vrain. The-scope of this program 'is-described.in the Performance Enhancement Program. - I* short, all components that have-historically be'en critical to plant reliability both from.a nuclear
- safety 4 and'a balance of plant perspective we're addressed.. Components falling into this category are identified 'as " critical ;significant components".
As a part of the maintenance procedure upgrade effort,.
the most current vendor equipment technical.information was obtained and incorporated
.as ' applicable, into plant procedures. Ongoing
- efforts in this area are expanding' the population of " critical significant components" as new concerns are identified through trend o
analysis or other means (e.g.,
IE Bulletins, INP0 ~SOER's, vendor equipment technical.information, etc.)
Administrative controls are currently being revised as a follow through to.the maintenance procedure upgrade and the vendor interface requirements of-Generic Letter 83-28 to require that all surveillance, maintenance, calibration, and.
testing procedures
. applicable to safety related components (including reactor trip system. component 5) be reviewed on a periodic basis, no longer than
' I every two years.
'This review will include requirements for contacting the vendors of applicable
" critical significant components" and obtaining updates to the vendor technical information as appropriate. The revised administrative controls are scheduled for implementation by December 31, 1987.
The interface that PSC has with its NSSS vendor, GA Technologies, is presumably unique to that of other licensees.
GA Technologies is treated no differently than any other vendor of safety related
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materials or services with respect to procurement requirements.
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LO Alt safety related components procured are required to.be accompanied.
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'with appropriate vendor equipment technical information in accordance j
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.with? FSV material receipt procedures (Administrative Procedure Q-4,-
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- Procurement System).. This. information is directed-to: a ' central-receiving-: point;in. the Nuclear Engineering Division:and is processed L~
.inlaccordance with Administrative Procedure G-15. Control-of Vendor
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' Manuals.
.This procedure further requires that.all vendor equipment L
technical information received be routed to the Operation Information:
Assessment.. Group _
for. review and. appropriate reference. and/or i
incorporation into' plant procedures in accordance with Administrative Procedure NPAP-1, Fort St. Vrain Nuclear Generating Station Operation-Information Assessment Group' Charter.
s All information received in the form of IE Bulletins, IE'Information l Notices, INP0 'Significant Operating Event Reports (S0ER's), etc.
is 1
processed' through the Operation Information Assessment' Group via the samtprocedure-(NPAP-1).
This assures that deficiencies identified
.elsewhere inLtthe-industry are systematically reviewed for
- applicability referenced _and/or incorporated into plant manue.ls and procedure.
This also serves to compensate for the-lack of a formal vendor interface in the ' case of the majority of safety -related components. where the, larger number (>2000) of. manufacturer / mode 1L numbers alone makes formal vendor interface impractical.
PSC provides information to the industry in the form of NPRDS reporting,. LER's, INP0 Significant Event Reports, I'NP0 Notepad entries, and Part 21 reports.
Even though specific portions of the Fort St. Vrain design'are unique, the majority of the steam system and plant protection system components are the same as those used elsewhere in the industry.
Safety related maintenance performed by vendors is normally performed using PSC procedures. Provisions do exist, however, for a vendor to use their own procedures in special cases provided that their QA program has been accepted by PSC in accordance with Administrative Procedure Q-2, Quality Assurance Program.
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