ML20238E396
| ML20238E396 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 09/11/1987 |
| From: | Grimsley D NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| To: | Gordon J Public Citizen's Critical Mass Energy Project |
| Shared Package | |
| ML20238E398 | List: |
| References | |
| FOIA-87-465, RTR-NUREG-1144 NUDOCS 8709140319 | |
| Download: ML20238E396 (4) | |
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J.6, NUCLEAR REGULATORY COMMISSION mRc FOlA REQU167 NUM8ERIS6 f0I A
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RESPONSE TO FREEDOM OF l"*
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INFORMATION ACT (FOIA) REQUEST i
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SEP 111987 q
e oock.tf NUMatR<ss in especeam REcuts R V
PART 1.-RECORDS RELEASED OR NOT LOCATED (See checked boxes)
No agency records sublect to the request have been located, No additonal agency records subsect to the request have been located.
[ Agency records subject to the request that are identifed in Appendix b
are already svailable for public enspection and copying in the NRC Public Document Room, 1717 H Street, N.W., Wsshington, DC.
]
Agency records subject to the request that are identifed in Appendix b
are being made available for pubhc inspection one copying in the NRC Public Document Room,1717 H Street, N W., Washington, DC, in a folder under the FOIA number and requester name.
The nonproprietary verson of the proposal (s) that you erysed to i ccept in a telephone conversation with a member of my staff is now being made avslable for public inspection and coying at the NRC Public Document Room,1717 H Street, N W., Washington, DC,in a fonder under this FOIA number and requester name.
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Enclosed is information on how you may obtain ar cess to and the Charges for copying records placed in the NRC Puolic Document Room,1717 H Street, N.W., Washington, '
Agency records subpoet to the request are enclosed. Any applicable charge for copes of the records provuled and payrnent procedures are noted in the comments secton.
Records subiect to the request have been referred to another Federal agencyles) for revow and direct response to you.
In view of NRC's response to this request, no further action a being taken on appeal letter dated PART lt.A-INFORMATION WITHHELD FROM PUDLIC DISCLOSURE Certain informaton in the requested records is being withheld from public disclosure pursuant to the FOlA exemptions described in and for the reasona stated in Part II, sec.
tions B, C, and D. Any released portions of the documents for which only part of the record is being wtthhel(1 are being made evallable for public inspecten and copying in the NRC Publec Document Room,1717 H Street, N.W,, Washington, DC, in a folder under this FOIA number and requester name.
Comments i
e stG Ct OR. D OF MV f ND RECORD i 8709140319 870911 e
Re: F01A-87-465 APPENDIX F RECORDS MAINTAINED AMONG PDR FILES
-1.
8/1/84 SECY-84-44A, subject: Nuclear Plant Reliability Data (NPRD) System.(26pages) Acces. No. 8408090367.
1 2.
2/8/85 SECY-85-56, subject: Nuclear Plant Reliability Data (NPRD) System. (22 pages) Acces. No. 8502200475.
3.
4/1985 Quality Assurance and Data Review of the Nuclear Plant Reliability-Data System, Third Quarter 1983 through Third Quarter 1984. Acces. No. 8505310188.
4.
June /85 NUREG/CR-4156, " Operating Experience and Aging - Seismic Assessment of Electric Motors," (150 pages) Acces. No.
8511180647 i
5.
8/20/85 SECY-85-56A, subject: Nuclear Plant Reliability Data (NPRD) System.(30pages) Acces. No. 8705180265.
6.
10/1985 Quality Assurance and Data Review of the Nuclear Plant Reliability Data System, Third Qtr.1983 - First Qtr.
1985. Acces. No. 8512190237.
7.
1/30/86 SECY-86-35, subject: Nuclear Plant Reliability Data (NPRD) System,(18pages). Acces. No. 8611100348, 8.
6/1986 NUREG/CR-4564, " Operating Experience and Aging - Seismic j
Assessment of Battery Chargers and Inverters, June 1986.
(138pages). Acces. No. 8610290256.
)
i 9.
2/24/87 SECY-87-54,
Subject:
Nuclear Plant Reliability Data System (NPRDS).(30pages) Acces. No. 8705180288.
- 10. March /87 Quality Assurance and Data Review of Nuclear Plant Reliability Data Systems, Third Quarter 1985 through Third Quarter 1986. Acces. No. 8704070280.
- 11. Undated NUREG/CR-4302, Aging and Service Wear of Check Valves
)
Used In Engineered Safety-Feature System of Nuclear Power Plant, Vol.1 (79 pages) Acces. No. 8601280340.
)
- 12. Undated NUREG/CR-4234, " Aging and Service Wear of Electric Motor
- Operated Yalves Used in Engineered Safety - Feature Systems of Nuclear Power Plants," Vol. 1 (124 pages)
Acces. No. 8507250149.
i
- 13. Undated NUREG/CR-4597, " Aging and Service Wear of Auxiliary Feedwater Pumps for PWR Nuclear Power Plant," Vol.1. (100 pa9es) Acces. No. 8609110306.
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Re: F01A-87-465 APPENDIX G RECORDS MAINTAINED IN THE PDR UNDER THE AB0VE REQUEST NUMBER 1.
1/30/84 Memo from C.J. Heltemes to addressee, subject: NPRDS Data Collection For RPS/ESFAS Instrumentation (2 pages) w/ enclosure: Control and Instrumentation. (10 pages) 2.
10/1/84 Memo from William J. Dircks to Office Directors, subject:
Evaluation of INP0 programs. (2 pages) 3.
9/1985 Evaluation of the Nuclear Plant Reliability Data System i
Component Boundary Document. (10 pages) 4.
1/9/86 Letter from C.J. Lovell to B.M. Brady, subject: NPRDS Quality Evaluation - CJL-2-86. (5 pages) 5.
7/22/86 Table 2. LER/NPRD-4 Comparison. (4 pages) 6.
8/8/86 Letter from C.J. Lovell to M.H. Williams, subject: NPRDS Data Comments - CJL-15-86. (4 pages) 7.
8/4/66 Memo from John E. Zerke to addressees, subject: NRC observation of INPO Program (1 page) w/ attachments:
a).
7/22/86 LettertoJ.R.BaumanfromJ. Crooks,(4 pages) b). 7/22/86 Memo from John Crooks to Marks Williams, subject: observations of INP0's Evaluation of the Operating Experience Program at McQuire. (11 pages) 8.
8/13/86 Note from Mark H. Williams to Lawrence Shao, subject:
AE0D's Input to the Technical Integration Review Group on Aging and Life Extension. (9 pages) 9.
12/31/86 Note from C.J. Heltemes to Victor Stello, subject: The attached Response to Bill Conway at INP0. (2 pages) 10.
1/28/87 DiscussionwithPeteLyonsandRonSimard(INP0), Meeting Notes. (4 pages)
- 11. 4/27/87 Memo from Thomas M. Novak to G.A. Arlotto, subject: Draft NPAR Program Plan - NUREG-1144, Revision 1 (AE0D Action Log #87-46)
(4 pages) w/ attached: Draft NPAR Program Plan
- NUREG-1144, Revision 1 comments. (156 pages) 12.
5/7/87 Memo from G.L. Plumlee to Mark H. Williams, subject: May 13-14, 1987 NPRDS Users Group Meeting. (3 pages)
n-Re: F01A-87-465 APPENDIX G (Continued) s
- 13. 6/24/87 Letter from R.L. Dennig to Paul G. Kuhel, subject:
Coments on Proposed Valve Failure Reporting Criteria'-
NPRDS Users Group (NUG) Meeting No.12 Action 4.5 (2 pages)w/ attachments: (1) NPRDS Valve Failure Reporting Criteria, May 1987 Draft From Commonwealth Edison (3 pages) (2) LER #86-008, Oyster Creek available under accession 8705050364.
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W UNITED STATES NUCLEAR REGULATORY COMMISSION og
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_t MEMORANDUM FOR: Harold R. Denton, Director, NRR Robert B. Minogue, Director, RES Richard C. DeYoung, Director, IE Regional Administrators FROM:
C. J. Heltemes, Jr., Director Office for Analysis and Evaluation of Operational Data
SUBJECT:
NPRDS DATA COLLECTION FOR RPS/ESFAS INSTRUMENTATION Your assistance is needed in defining reportable components for use by licensees in reporting engineering and failure data for RPS/ESFAS instrumentation to the
.NPRD System.- Your response is requested by February 15, 1984.
The. subicission of engineering pedigree data in advance of reporting failures comprises a large part of the NPRD System reporting burden. For complex electronic systems such as the RPS and ESFAS, the burden can be overwhelming given the profusion of relays, rectifiers, modules, circuit boards, switches, power suppliet, etc., if such items are defined as reportable components, each requiring a separate engineering data pedigree report. On the other hand,- if the reportable component boundary is defined at a higher level, an instrument drawer for example, there is concern that no two drawers will be alike and component comparability will be lost.
INPO would like to define reportable components for RPS/ESFAS in a way which is compatible with basic event definitions in PRA (failure rate calculation) or other reliability modeling.
They are interested in determining user needs for 1
the types ' of components which are modeled and for associated population data (the major reason for requiring engineering pedigree data prior to a failure occurring). In order to assist INPO, we request your response to the following
. questions:
1 1.
What are your needs for engineering data records (i.e., NPRD-2 forms) prior l
i to failure on RPS/ESFAS instruments other than sensors / transmitter? What l
are the component boundary definitions?
INPO is only sure at this time of the need for populatica data for sensors /
l primary transmitters such as neutron detectors, pressure transmitters, level i
detsetors, RIDS, etc., and feels that the boundaries of these components I
are rather clear. INPO does not have good component boundary definitions for items wh!.ch perform processing or conditioning functions for cutputs from sensors / primary transmitters. An example is a pressurizer level detector l
signal processing drawer. Further, INFO is not sure if failure rates need
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to be calculated for such things and is considering a policy of not requiring engineering data until a failure has occurred.
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- 2. 'If you'need population data for RPS/ESFAS signal processing instruments,
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do you know of sources of that information other than NPRDS?
l In relation to. question 1, maintenance,of electronic systems most often 3.
involves replacement of a circuit " card" or a " module" in an instrument drawer or cabinet. Do you require population data for " cards" or " modules"?
Have you ever used or attempted to use NPRD System data on RPS/ESFAS l
4.
instruments?. If so, did you have any problems and/or do you have any suggestions for improvements in retrieving and using the information?
Have you ever conducted a f ault tree-type analysis of RPS/ESFAS
.5.
instrumentation at the " card" or " module" (a " module" plugs into a circuit If board and performs a particular logic of processing function) level?
yes, please provide samples of your analysis for INPO to review. If no, please indicate the level that you have modeled and would you provide an example?
If you have any questions regarding our request, please contact Bob Dennig at 24491.
OI C.l Heltem Jr., Director Of e for Analysis and Evaluation of Operational Data cc AThadani, NRR GBurdick, RES CRossi, IE GHolahan, NRR f
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OCT L SM ii MEMORANDUM FOR:
Office Directors Regional Administrators FROM:
William J. Dircks Executive Director for Operations
SUBJECT:
EVALUATIONS OF INPO PROGRAMS
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We need to evaluate the effectiveness of INP0 programs as a necessary step in dec' ding whether on-going and evolving NRC programs should be modified because of INPO programs tha: have similar objectives. Without a reasonable indication of the effectiveness of INPO programs, it would be difficult for NRC to adjust its programs in recognition of INPO activities that may complement the NRC mission.
Adjustments of NRC programs because of INPO activities should be based on NRC staff first-hand knowledge of the INPO programs. The relationship between NRC and INPO regarding program evaluation must be direct, and not rely upon consul-tants, contractors, or other third parties.
In other words, we should use NRC staff to evaluate INPO programs and not contractors.
In the rare event special expertise not'available within the NRC staff is-necessary in order to evaluate an INPO program, the specifics should be reviewed with Jim Sniezek who will consider the circumstances and, if warranted, will. interface with INPO on the matter.
Please ensure that your managers are aware of this policy.
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Willia J. Dircks Executi i Director for Operations l
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'ZT.8 Addressees for Memorandum fm W. J. Dircks Dated DCT 1 1934 P. G. Norry, ACM -
C. J.. Hel temes, AE00 G. Cunningham, ELD R. C. DeYoung. IE H. R. Denton, NRR J."G. Davis,'iMSS J. Shea, IP G.
. Kerr, SP L. Barry, RM R. B. Minogue, RES T. E. Murley, R-I i
J. P. O'Reilly, R-II J. G. Keppler, R-III
~i J. T. Collins, R-IY J. B. Martin,. R-V.
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