ML20137G272

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Advises of Safeguards Regulatory Effectiveness Review Scheduled for 850805-09.Review Will Evaluate Overall Effectiveness of Safeguards Program to Determine If Level of Protection Intended by NRC Met
ML20137G272
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 07/26/1985
From: Johnson E
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To: Lee O
PUBLIC SERVICE CO. OF COLORADO
References
NUDOCS 8508270253
Download: ML20137G272 (3)


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JUL 2/o 1985 In~ Reply Refer-To:

Docket: 50-267 Public Service Company of Colorado ATTN: 0. R. Lee, Vice President Electric Production P. O. Box 840 v Denver, Colorado 80201 Gentlemen:

The NRC is in process of conducting Safeguards Regulatory Effectiveness Reviews at nuclear power reactors. I wish to inform you that the Fort St. Vrain facility has been chosen for such a review scheduled for the week of August 5 through 9, 1985.

The prime purpose of the review program is to evaluate the overall effectiveness of the Fort St. Vrain safeguards program and to determine whether existing safeguards regulation yield the level of protection intended by NRC.

The team performing the review supports NRC's quality assurance program for safeguards, both as it applies to the Fort St. Vrain security system and to NRC's regulations. The review will complement, but be independent of, the licensing and inspection functions.

The review at Fort St. Vrain will be conducted by a team with representatives from the Office of Nuclear Materials Safety and Safeguards, Region IV, and U.S. Army Special Forces personnel from Fort Bragg, North Carolina. The review team will be comprised of two groups. One group will look at the facility's safeguards from the perspective of an insider, while the other will view safeguards from an external adversary's perspective.

The review will initiate with an entrance briefing. You may wish to have a representative of your corporate staff present during this briefing, as it will provide an overview of the team's objectives and anticipated activities for the duration of the visit. Any questions that may arise concerning the team's review technique or other matters, will be addressed at that time. For the remainder of the first day, the team would like to have a plant orientation tour with emphasis on safeguards areas and systems, and begin the examination of plant vital areas. During the remainder of the onsite assessment, the team

-will continue reviewing vital areas and components, and the entire safeguards program. The last day is reserved for any activities the team has been unable i to accomplish and for a briefing of plant and corporate personnel on the i preliminary results of the review.

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Public Service Company of Colorado Please provide appropriate plant personnel support for both groups of the team during the scheduled review. The external group will require an escort from the security department who can communicate with alarm stations. The internal group will need escorts from both security and plant operations. The latter should be individuals familiar with the locations and detailed operation of the engineered safety feature systems and components. The team will make every effort to schedule its activities so as to minimize disruption of normal plant operations. The time that various team members will spend onsite will vary, but generally will range from four to seven hours per day.

Listed below are the names of the participants, badga number and level of clearance.

Name Organization Badge Number Clearance Barry Mendelson NRC/HQ A-0970 Q David Orrik NRC/HQ B-3174 L Greg Dailey U.S. Army ASF L Jack Pope U.S. Army ASF L Zan-Shing R. Hsu NRC/HQ B-3213 L Carol Rossomondo NRC/HQ A-2330 Q Rocio Gallegos NRC/HQ A-3316 Q If you have any questions regarding the conduct of these regulatory effectiveness reviews, which you wish to have answered prior to the team's l visit, please contact Barry Mendelson, Safeguards Special Projects Branch, at (301) 427-4721 or R. A. Caldwell (817 860-8132) of the Region staff.

Sincerely, j Origina! Signed By E. H. Johnson E. H. Johnson, Chief Reactor Projects Branch cc: J. W. Gahm, Manager, Nuclear

, Production Division j Fort St. Vrain Nuclear Station i

16805 WCR 19h Platteville, Colorado 80651 L. Singleton, Manager, Quality Assurance Division (same address)

Colorado Radiation Control Program Director

Public Service Company of Colorado ZF3' bcc to DMB (A0467 bec distrib. by RIV:

RPB1 R. P. Denise, DRSP Resident Inspector R. D. Martin, RA Section Chief (RPB1/SPES) E. Haycraft, LA P. Wagner, RPB1 J. B. Baird, EP&SPS D. Powers, RPB1 R. L. Bangart, DRS&S R&SPB N. M. Terc, EP&SPS RIV File C. A. Hackney, EP&SPS R. Burnett, NMSS