ML13330A763
| ML13330A763 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 09/07/1979 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Arenal A SOUTHERN CALIFORNIA EDISON CO. |
| References | |
| NUDOCS 7909240169 | |
| Download: ML13330A763 (6) | |
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sUNITED STATES o g NUCLEAR REGULATORY COMMISSION REGION V 1990 N. CALIFORNIA BOULEVARD SUITE 202, WALNUT CREEK PLAZA WALNUT CREEK, CALIFORNIA 94596 September 7, 1979 Docket No. 50-206 Southern California Edison Company P. 0. Box 800 2244 Walnut Grove Avenue Rosemead, California 91770 Attention: Mr. A. L. Arenal Vice President, Advanced Engineering Gentlemen:
The enclosed Supplement 2 to Bulletin No. 79-14 is forwarded to you to provide added guidance on the intent of the Bulletin. If you desire additional information regarding this matter, please contact this office.
Sincerely, R. H. Engelken Director
Enclosures:
- 1. Supplement 2 to IE Bulletin No. 79-14
- 2. List of IE Bulletins Issued in Last Six Months cc w/enclosures:
J. T. Head, SCE J. M. Curran, SCE, San Clemente 7 9092 40J4kr3l
SSINS:
6820 Accesstion No.: 7908220109 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C. 20555 September 7, 1979 IE Bulletin No. 79-14 Supplement 2 SpEiMi ANA!.S FOR AS-BUILT SAFTY-RELATE PIPING SYSTEMS Description of Circumstances:
IE Bulletin No. 79-14 was issued on July 2, revised on July 18, and first supplemented on August 15, 1979. The bulletin requested licensees to take certain actions to verify that seismic analyses are applicable to as-built plants. Supplement 2 provides the following additional guidance with regard to implementation of the bulletin requirements:
Nonconformances One way of satisfying the requirements of the bulletin is to inspect safety related piping systems against the specific revisions of drawings which were used as input to the seismic analysis. Some architect-engineers (A-E) however, are recommending that their customers inspect these systems against the latest revisions of the drawings and mark them as necessary to define the as-built configuration of the systems. These drawings are then returned to the AE's offices for comparison by the analyst to the seismic analysis input. For licensees taking this approach, the seismic analyst will be the person who will identify nonconformances.
The first supplement to the bulletin provided guidance with regard to evaluation of nonconformances. That guidance is appropriate for licensees inspecting against later drawings. The licensee should assure that he is promptly notified when the AE identifies a nonconformance, that the initial engineering judgment is completed in two days and that the analytical engineering evaluation is completed in 30 days. If either the engineering judgement or the analytical engineering evaluation indicates that system operability is in jeopardy, the licensee is expected to meet the applicable technical specification action statement.
Visual Approximations Some licensees are visually estimating pipe lengths and other inspection elements, and have not documented which data have been obtained in that way.
Visual estimation of dimensions is not encouraged for most measurements; however, where visual estimates are used, the accuracy of estimation must be within toler ance requirements. Further, in documenting the data, the licensee must specif ically identify those data that were visually estimated.
IE Bulletin No. 79-14, Supplement 2 September 7, 1979 Page 2 of 2 Thermal Insulation In many areas, thermal insulation interferes with inspection of pipe support details, i.e. attachment welds, saddles, support configuration, etc. In some areas, the presence of thermal insulation may result in unacceptably large.
uncertainties for determination of the location of pipe supports.
Where thermal insulation obstructs inspection of support details, the insulation should be removed for inspection of a minimum of 10% of the obstructed piDe suDoorts in T
i ci In the Item response, the licensee should include a schedule for inspecting the remaining supports.
Where necessary to determine the location of pipe supports to an accuracy within design tolerances, thermal insulation must be removed.
Clearances For exposed attachments and penetrations, licensees are expected to measure or estimate clearances between piping and supports, integral piping attachments (e.g. lugs and gussets) and supports, and piping and penetrations. Licensees are not expected to do any disassembly to measure clearances.
Loose Bolts Loose anchor bolts are not covered by this bulletin, but are covered by IE Bulletin No. 79-02. Any loose anchor bolts identified during actions taken for this bulletin should be dispositioned under the requirements of Bulletin No. 79-02.
Other loose bolts are to be treated as nonconformances if they invalidate the seismic analysis; however, torquing of bolts is not required.
Difficult Access Areas where inspections are required by the Bulletin but are considered impractical even with the reactor shutdown, should be addressed on a case by case basis.
Information concerning the burden of performing the inspection and the safety consequence of not performing the inspection should be documented by the licensee and forwarded for staff review.
Schedule The schedule for the action and reporting requirements given in the Bulletin as originally issued remains unchanged.
IE Bulletin No. 79-14, Supplement 2 Enclosure September 7, 1979 Page 1 of 3 LISTING OF IE BULLETINS ISSUED IN LAST SIX MONTHS Bulletin Subject Date Issued Issued To No.
79-22 Possible Leakage of 9/5/79 Each Licensee who Tubes of Tritium Gas Receives Tubes of Used in Timepieces for Tritium Gas in Luminosity Timepieces for Luminosity 79-13 Cracking in Feedwater 8/30/79 All Designated (Rev.
- 1)
System Piping Applicants for OLs 79-21 Temperature Effects 8/13/79 All PWRs with on Level Measurements an operating license 79-20 Packaging Low-Level 8/10/79 All Materials Licensees Radioactive Waste for who did not receive Transport and Burial Bulletin No. 79-19 79-19 Packaging Low-Level 8/10/79 All Power and Research Radioactive Waste for Reactors with OLs, Transport and Burial fuel facilities except uranium mills, and certain materials licensees 79-18 Audibility Problems 8/7/79 All Power Reactor Encountered on Evacuation Facilities with an Operating License 79-17 Pipe Cracks in Stagnant 7/26/79 All PWR's with Borated Water Systems at operating license PWR Plants 79-16 Vital Area Access Controls 7/26/79 All Holders of and applicants for Power Reactor Operating Licenses who anticipate loading fuel prior to 1981.
79-05C&06C Nuclear Incident at Three 7/26/79 To all PWR Power Mile Island - Supplement Reactor Facilities with an OL 79-15 Deep Draft Pump 7/11/79 All Power Reactor Deficiencies Licensees with a CP and/or OL
IE Bulletin No. 79-14, Supplement 2 Enclosure September 7, 1979 Page 2 of 3 LISTING OF IE BULLETINS ISSUED IN LAST SIX MONTHS Bulletin Subject Date Issued Issued To No.
79-14 Seismic Analyses for 6/2/79 All Power Reactor As-Built Safety-Related facilities with an Piping System OL or a CP 79-01A Environmental Qualification 6/6/79 All Power Reactor of Class 1E Equipment Facilities with an (Deficiencies in the Envi-OL or CP ronmental Qualification of ASCO Solenoid Valves) 79-13 Cracking In Feedwater 6/25/79 All PWRs with an System Piping OL for action. All BWRs with a CP for information.
79-02 Pipe Support Base Plate 6/21/79 All Power Reactor (Rev. 1)
Designs Using Concrete Facilities with an Expansion Anchor Bolts OL or a CP 79-12 Short Period Scrams at 5/31/79 All GE BWR Facilities BWR Facilities with an OL 79-11 Faulty Overcurrent Trip 5/22/79 All Power Reactor Device in Circuit Breakers Facilities with an for Engineered Safety OL or a CP.
Systems79-05B Nuclear Incident at Three 5/21/79 All B&W Power Reactor Mile Island Facilities with an OL 79-10 Requalification Training 5/11/79 All Power Reactor Program Statistics Facilities with an OL 79-06A Review of Operational 4/18/79 All Pressurized Water (Rev 1)
Errors and System Mis-Power Reactor Facilites alignments Identified of Westinghouse Design During the Three Mile with an OL Island Incident 79-09 Failures of GE Type AK-2 4/17/79 All Power Reactor Circuit Breaker in Safety Facilities with an Related Systems OL or CP
IE Bulletin No. 79-14, Supplement 2 Enclosure September 7, 1979 Page 3 of 3 LISTING OF IE BULLETINS ISSUED IN LAST SIX MONTHS Bulletin Subject Date Issued Issued To No.
79-08 Events Relevant to BWR 4/14/79 All BWR Power Reactor Reactors Identified During Facilities with an OL Three Mile Island Incident 79-07 Seismic Stress Analysis 4/14/79 All Power Reactor of Safety-Related Piping Facilities with an OL or CP 79-06B Review of Operational 4/14/79 All Combustion Engineer Errors and System Mis-ing Designed Pressurized alignments Identified Water Power Reactor During the Three Mile Facilities with an Island Incident Operating License 79-06A Review of Operational 4/14/79 All Pressurized Water Errors and System Mis-Power Reactor Facilities alignments Identified of Westinghouse Design During the Three Mile with an OL Island Incident 79-06 Review of Operational 4/11/79 All Pressurized Water Errors and System Mis-Power Reactors with an alignments Identified OL except B&W facilities During the Three Mile Island Incident 79-05A Nuclear Incident at 4/5/79 All B&W Power Reactor Three Mile Island Facilities with an OL 79-05 Nuclear Incident at 4/2/79 All Power Reactor Three Mile Island Facilities with an OL and CP