ML20246E328
| ML20246E328 | |
| Person / Time | |
|---|---|
| Issue date: | 03/05/1987 |
| From: | Beckjord E NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | Fraley R, Sniezek J Advisory Committee on Reactor Safeguards, Committee To Review Generic Requirements |
| Shared Package | |
| ML20149C371 | List:
|
| References | |
| NUDOCS 8905110227 | |
| Download: ML20246E328 (3) | |
Text
_ - -_ _ - - - . - -
't
- 'o UNITED STATES h 8 o NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 4
\
%.....) W5 1987 i
MEMORANDUM FOR: James H. Sniezek, Chairman Committee to Review Generic Requirements Raymond F. Fraley, Executive Director Advisory Committee on' Reactor Safeguards FROM:
Eric S. Beckjord, Director Office of Nuclear Regulatory Research
SUBJECT:
REQUEST FOR APPROVAL TO PUBLISH A FEDERAL REGISTER NO
.AND DISTRIBUTE A GENERIC LETTER DEALING WITH SRP 3.6.2 On December 3,1986, a . Federal Register notice (Enclosure 1) was published under my signature soliciting public comment on a proposed revision Thetoproposed Branch Technical Position MEB 3-1 of Standard Peview Plan Section 3.6.2.
revision described in the Federal Register notice and transmitted to the Commission's Public Document Room was identical to that approved by the CRGR on September 17, 1986, but did not accept one recommendation made by the ACRS in a This recommendation
-letter dated November 12, 1986 to the EDO (Enclosure 2). resulting dealt with compartment, subcompartment and cavity pressurization b from arbitrary intermediate pipe ruptures.
On December 18, 1986, the EDO responded to the ACRS letter noting that (see Enclosure 3):
"We disagree with your recommendation to retain in part the effects of an eliminated postulated pipe rupture for a number of reasons."
Elsewhere in the same letter, the ED0 states:
"Phile we do not agree with revising Standard Review Plan (SRP) 3.6.? to address the Committee [ACRS) recommendation, the staff would be pleased to ireet with appropriate Committee (ACPS] members to discuss their (Emphasis concerns and see if they can be accommodated in other ways" added).
notice, two public In response to the December 3, 1926 Federal Pegister comment letters reising three issues were received (Enclosure 4). The two public comment letters did r.ot require any change to the proposed revision to Branch Technical Position PEB 3-1; only explanations and clarifications are needed. Enclosure 5 contains the Federal Register notice of Issuance which addresses the questions raised in public comment. At the request of the CRGR, 8905110227 070507 PDF. REVGP NRCCRGR MEETING 112 PDC
- i l*~ James H. Sniezek 2 MAR 5' 1987 l Raynond F. Fraley we have also prepared a Generic letter advising licensees, construction permit-holders and applicants for construction permits of this action (Enclosure 6).
l Your approval to publish Enclosure 5 and distribute Enclosure 6 is reauested I by this memorandum. For completeness and ease of review, Enclosure 7 contains
, the retyped MEB 3-1 which would substitute for the existing version of PEB 3-1.
Heavy bars in the margins indicate locations where MEB 3-1 has been amended.
A tO ] & iU rG Eric S. Beckjord,U)irector Office of Nuclear Regulatory Research
Enclosures:
- 1. Federal Register notice of Availability (December 3,1986)
- 2. ACRS letter of November 12, 1986
- 3. ED0 letter of December 18, 1986
- 4. Comment letters received
- 5. Federal Register notice of Issuance (proposed)
- 6. Generic Letter (proposed)
- 7. Revised MEB 3-1 9
Sb i
I E.Wl-O$UW
\
. Federal Register / Vol. St. No. 232 / Wednesday. December 3.1986 / Notices 43695 Office. Post Office Box 37082. considerations; specifically. (1) 4000. Maryland National Bank Building.
Washington. DC 20013-7082. telephone differential pressurization due to 7735 Old Georgetown Road. Bethesda.
(202) 275-2060 or (202) 275-2171. Issued terminal end breaks. due to intermediate Maryland. 20014. Comment period guides may also be purchased from the breaks at high stress and high usage expires January 20.1987. Comments National Technical Information Service factor locations and due to leakage received after this date will be on a standing order basis. Details on cracks are still required. (2) double- considered ifit is practical to do so but this service may be obtained by writing ended pipe ruptures are rare events. assurance of consideration can only be NTIS. 5285 Port Royal Road. Springfield, double-edd pipe ruptures at given to comments received on or before VA 22161. intermediate ecations are very rare this date.
events (only abt ut 10% of all pipe The proposed revision to Branch (5 0.S C. 552(all Dat.d at Hot kulle. Star >!and this 20th da).
failures occur at intermediate locations). Technical Position MEB 3-1 of Standard nf Nowmher 1980. and double-ended pipe ruptures at Review Plan section 3.6.2 and the For the Nuclear Regulatory Commission.
selected arbitrary (low stress) Regulatory Analysis pertaining to this intermediate locations are extremely revision are available for inspection at Eric S. Beckjord, rare events. the Commission's Publi:: Document B.' rector. Office of Nuc/cor Reg flatory A regulatory analysis prepared by Room.171711 Street NW., Washington.
Research.
Lawrence livermore National DC.
(FR Doc. 86-27194 Filed 12-2-86. 8:45 am] Laboratory has indicated that cost Dated at Rockville. Merytand this 25th day savings of.c1? million and averted of November 19ao.
occupational radiation exposures of For the Nuclear Regulatory Commission.'
Standard Review Plan; Availability 17.000 men rem could result from the proposed revision without any m S. %d Director. Ofhce of NuclearRegulatory The Nuclear Regulatory Commission significant increase in public risk. The RuearcA
' (NRC)is issuing for public comment a regulatory analysis did not identify (FR Doc. 86-27195 Filed 12-2-80; 8.45 aml revison to Branch Technical Position differential pressurization as an important contributor to the values and 8" C** '5***
MED 3-1 of Standard Review Plan section 3.6.2 in NUREG-o800. The impacts associated with the elimination revision would change requirements of arbitrary intermediate pipe ruptures from the design basis, but instead (DockeWo. 5M7]
relating to postulated arbitrary intermediate pipe ruptures in Class 1. 2 focused on the removal of pipe whip Mississippi Power & Light Co. et af; and 3 piping as specified in B.1.c.(1)(d) restramts and jet impingement barriers. Transfer of Controlof Construction and B.1.c.(2)(b)(ii) of Branch Technical Arbitra,ry intermediate pipe ruptures Permit for Grand Gulf Nuclear Station, Position MEB 3-1. Other postulated were ongmally postulated more than Unit 2 intermediate pipe ruptures and terminal fifteen years ago to provide greater end ruptures would not be affected in assurance that conservatism is Notice is hereby given that the United the proposed revision. Dynamic effects maintained, particularly with respect to States Nuclear Regulatory Commission (missile generation, pipe whipping, pipe consequences on equipment.The U.S. (Commission)is considering approval break reaction forces, jet impingement Nuclear Reguatory Commission Pipin6 under 10 CFR 50.80 of the transfer of forces and decornpression waves within Review Committee in NUREG-1061. control of the Grand Gulf Nuclear the ruptured pipe), and environmental Volene 5 dated April 1985. Station Unit 2 construction permit from effects (preseure, temperature. humidity recommended that arbitrary Mississippi Power and Light Company and flooding) resulting from arbitary intermediate pipe ruptures should be (MP&L) to a nuclear generating intermediate pipe ruptures would be deleted from the design basis because company. System Energy Resources. Inc.
eliminated from the design basis under they complicate pipe system design. (SERI) formerly named Middle South the proposed revision. The NRC staff increase costs of design, degrade the Energy.Inc.(MSE). Ownership of t'ne and the NRC Committee to Review effectiveness of inservice inspection. Grand Gulf Nuclear Station. Unit 2 will Generic Requirements recommended increase heat losses from piping and be unchanged, being 90% owned by MSE that in addition, compartment, could cause unanticipated thermal (now SERI) and 10% owned by the South subcompartment and cavity differential expansion stress (with associated crack Mississippi Electric Power Association pressurization associated with growth). (SMEpA). MP&L and MSE (now SERI) arbitrary intermediate pipe ruptures Under the proposed revision. are subsidiaries of Middle South should also be elminated from the licensees of operating plants desiring to Utilities. Inc. and SMEPA is an design basis.The NRC Advisory eliminate effects of arbitrary association of rural electric Comrnittee on Reactor Safeguards intermediate pipe ruptures may do so cooperatives. By letter dated September
( ACRS). however, has recommended without prior Commission approval 2.1986. as amended by letters dated that these compartment, unless such changes conflict with the October 4.13 and 24.1986, the joint subcompartment and cavity differential license or technical specifications. licensees informed the Commission that pressurization should be retained in the Approximately fifteen utilities have on July 22.1986 the Board of Directors of design basis even when other effects of already taken advantage of this Middle South Utilities had taken action albritary intermediate pipe rupture are relaxation since 1984. to rename MSE as SERI and to authorize climinated. While this latter Public comment is solicited on this transferring to SERI all responsibilities recommendation le still being proposed revision. particularly with for the operation of Unit 1 and the deliberated within the NRC. the position regard to the differential pressurization construction of Unit L Notice of stated in the proposed revision allows issue described above. Comment letters Consideration ofIssuance of the elimination of differential should be sent to: Michael Lesar, Acting Amendment to Facility Operating pressurization due to arbitrary Chief. Rules and Procedures Branch, licenses, containing notice of the intermediate pipe ruptures.This Division of Rules and Reccrds. U.S. proposed transfer oflicense for Grand decisiords based on a number of Nuclear Regulatory Commission. Roorn Gulf Nuclear Station Urat I was
_ _ _ _ _ _ _ _ - _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _