ML20195G716
| ML20195G716 | |
| Person / Time | |
|---|---|
| Issue date: | 10/19/1987 |
| From: | Murley T Office of Nuclear Reactor Regulation |
| To: | Beckjord E NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| Shared Package | |
| ML20154D839 | List: |
| References | |
| REF-GTECI-A-47, REF-GTECI-SY, TASK-A-47, TASK-OR NUDOCS 8711050137 | |
| Download: ML20195G716 (2) | |
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00T 191987 f,
l MEMORANDUM FOR:
Eric S. Becyord Director Of fice of Nuclear Regulatory Research g.
FROM:
Thomas E. Murley, Director Of fice of Nuclear Reactor Regulation
SUBJECT:
REVIEW OF CRGR PACKAGE FOR PROPOSED RESOLUTION OF f
A 47 "SAFETY IMPLICATIONS OF CONTROL SYSTEMS IN tWR NUCLEAR POWER PLANTS" As requested by your note dated May 6,1987, we have reviewed the proposed resolution of Unresolved Safety Issue (USI) A-47, "Safety laplications of Control Systems in LWR Nuclear Power Plants." As you are aware, we have been providing comments regarding the US! A-47 resolution since September,1964.
i Based on our latest review, we provided under separate cover a set of comments (technical and editorial) to the Task Manager (Andy Szt.kiewicz). My technical l
staf f met with your staf f on May 21 and 22 and discussed these technical and editorial comments. Within the constraints of the identified scope of this j
l issue, the comments have been resolved and where appropriate incorporated in the resolution package.
We recognize that certain limitations and rules had to be estabilshed so that l
a study of such magnitude (e.g., USI A 47) could be confined to a workable
,l program.
As can be expected, this narrowed the scope for the US! A-47 study.
However, we would like to make the following observation and recommendations:
l i
(1) We believe that the proposed resolution of US! A 47 is closely coupled i
with the ongoing B&WOG reassessment atudy effort.
On the basis of consideration of the safety benefit derived in terms of risk reduction and the cost of implementation, the proposed resolution of US! A-47 4
imposes only a few requirements mostly dealing with steam generator
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overfill protection.
Although loss of power transients were evaluated t
for the reference plants, the U51 A-47 scope assumed that plant-specific 1
designs were appropriately modified to comply with IE Bulletin 79 27,
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"Loss of Non-Class IE Instrumentation and Control Power System tus During Operation."
In a newarandum dated June 1,1942 from R. Mattson to D. Eisenhut, it was stated that the broader laplications of this issue (79-27) would be addressed as part of the USI A 47 study.
No i
additional concerns were identified as part of the USl A-47 review; however, the 1985 event at Rancho Seco demonstrated that Rancho Seco's conformance to and implementation of IEB 79-27 wre inadequate.
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Contact:
J. Mauck (SIC 8/ DEST) x-24417 I
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..Erty 5. Beckjord 2-g ig g I
lhe rWOG has submitted recommendations to the staf f that the owners group considers prudent to make for improving the reliability of the ICS and reducing the challenges to safety systems.
Included in this study is a reevaluation of conformance to and implementation of IE Bulletin 79 27.
We are concerned that the staf f's acceptance of the proposed resolution of U5l A-47 at this time may be misinterpreted by industry and would negatively influence and act as a disincentive in the outcome of the B&WOG reassessment effort.
This would place the staff in a weak position to negotiate with the B&WOG for improvements to the ICS as well as other control systems in the B&W operating plants and, perhaps, control systems in other N555 operating plants.
Although we concur with the technical findings and recommend that this package go forward with the CRGR and ACRS review, we request that issuing the proposed resolution be withheld from public comment until the reassessment ef fort, by the BWOG and the staff, dealing with the ICS is completed (currently scheduled for January,1988).
(2) An underlying theme throughout the US! A-47 report is that there are ongoing studies (i.e., USI A 46) and pregrams which will provide answers and resolations to several related issues.
We were somewhat concerned thn not all the irsues noted as being part of another study would, in fact.
be resolved as discussed in USI A-47.
We recommended that an interface section be provided in a matrix form so that the users of this document (staf f/ industry) can rapidly pull together the carryover from this program i
which will be resolved cnder ongoing Unresolved Safety Issues or Generic i
issues.
This matrix could also identify to other task managers follow-up work that they have to consider during resolution of their issue.
P As a result of our earlier conversation and our concerns regarding the i
implementation of the proposed U5! A 47 requiroents, the generic letter has been revised by ElB.
Also, to expedite the licensees' responses to the generic letter and the ensuing staff reviews, a typical Sholly and a generic Safety Evaluation including appropriate model technical specifications are included as part of the U51 A 47 CRGR package.
As discussed in item 2 above, a matrix table I
summarizing related issues to 051 A-47 has also been included as part of the l
package.
Based on the satisfactory resolution of the above recommendation regarding publication of the proposed resolution, we concur with the U5! A 47 package to be issued to CRCR.
I ?!KW-Thomas E. Murley, Ofrector Office of Nuclear Reactor Regulation cc:
G. Arlotto A. Szukiewicz F. Miraglia F. Hebden 1
J. Blaha R. Baer l
J. Funches P. Cota
December 11,1987
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l MEMORANDUM FOR:
Robert M. Bernero, NMS$
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l Thomas T. Martin, Region !
Denwood F. Ross, RES t
l Joseph Scinto, OGC James H. Sniezek, NRR
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FROM:
Edward L. Jordan, Chairman Committee to Review Generic Requirements
SUBJECT:
TRANSMITTAL OF REVIEW PACKAGE FOR CRGR MEETING NO. 127 l
l The NRC staff's proposed resolution for USI A-47, "Safety Implications of Control Systems..." has been tentatively scheduled for review by CRGR at Meeting No. 127 which would normally occur on December 23, 1987.
This review package is being distributed to CRGR members in advance of finalizing arrange-l ments for Meeting No. 127 to allow members to begin review of the relatively large amount of material that will be involved in the review of this issue.
The relationship of A-47 to the B&W design reassessment effort will be considered as part of the Comittee's review of this USI.
Also enclosed is the initial (partial) E' issued recently by the staff documenting their review to date of the B&W Owners Group reassessment offort, bishaf Sigw af, L D Ja dsn Edward L. Jordan, Chairman Committee to Review Generic 1
i Requirements i
Enclosures:
f As stated cc w/ enclosures:
Distribution:
SECY E. Jordan V. Stello, Jr.
J. Heltemes l
J. Conran cc w/o enclosures:
(C. Setenes
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Comission (5)
R. Fraley J. Lieberman CRGR CF (w/o enc.)
l S. Ebneter CRGR SF t
W. Mcdonald S. Treby (w/o ene.)
Regional Administrators T. Rehm (w/o enc. )
W. Parler J. Johnson, OEDO R. Hernan POR (NRC/CRGR) (w/o enc.)
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