ML19249B903
| ML19249B903 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/15/1979 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Cavanaugh W ARKANSAS POWER & LIGHT CO. |
| References | |
| NUDOCS 7909070064 | |
| Download: ML19249B903 (1) | |
Text
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August 15, 1979 Docket Nos.
50-313 50-368 Arkansas Power and Light Company ATTN:
Mr. Willian Cavanaugh Ill Vice President of Generation and Construction P. O. Box 551 Little Rock, Arkansas 72203 Gentlemen:
The enclosed supplement to IE Bulletin 79-14 is forwarded to you to provide added guidance on the intent of the lE Bulletin.
If you desire additiot.a1 information regarding this matter, please contact this office.
Sincerely, f
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N')f)Lk'f)W &{
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Karl V. Seyf rip' [
Director
Enclosures:
1.
Supplement lE Bulletin No. 79-14 2.
List of IE Bulletins Issued in the Last Six Months cc:
James P. O'Hanlon, Plant Manager Arkansas Nuclear One P. O. Box 608 Russellville, Arkansas 72801 Id{
7909070064
UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEt1ENT WASHINGTON, D.C.
20555 Supplement IE Bulletin No. 79-14 Date: August 15, 1979 Page 1 of 2 SEISMIC ANALYSIS FOR AS-BUILT SAFETY-RELATED PIPING SYSTEMS lbscription of Circumstances:
IE Bulletin No. 79-14 was issued on July 2, 1979, and revised on July 18, 1979.
The Buitetin requested licensees to take certain actions to verify that seismic analyses are applicable to as-built plants.
This supplement to the Bulletin provides cdditional guidance and definition of Action Items 2, 3, and 4.
To comply with the requests in IE Bulletin 79-14, it will be necessary for licensees to do the following:
2.
Inspect Part of the Accessible Piping For each system selected by the licensee in accordance with Item 2 of the Bulletin, the licensee is expected to verify by physical inspection, to the extent practicable, that the inspection elements meet the acceptance criteria.
In performing these inspections, the licensee is expected to use measuring techniques of sufficient accuracy to demonstrate that acceptance criteria are met.
Where irspection elements important to the seismic analysis cannot be viewed because of thermal insulation or location of the piping, the licensee is expected to remove thermal insulation or provide access. Where physical inspection is not practicable, e.g., for valve weights and materials of construction, the license is expected to verify conformance by inspection of quality assurance records.
If a nonconformance is found, the licensee is expected in accordance with Item 4 of the Bulletin to perform an evaluation of the significance of the nonconformance as rapidly as possible to determine whether or not the operability of the system might be jeopardized during a safe shutdown earthquake as defined in the Regulations.
This evaluation is expected to be done in two phases involving an initial engineering judgement (within 2 days), followed by an analytical engineering evaluation (within 30 days). Where either phase of the evaluation shows that system operability is in jeopardy, the licensee is expected to meet the applicable technical specification action statement and complete the inspections required by Item 2 and 3 of the Bulletin as soon as possible. The licensee must report the results of these inspections in accordance with the require-ments for content and schedule as given in Item 2 and 3 of the Bulletin.
p>c 1 !i 2
Supplement IE Bulletin No. 79-14 Date: August 15, 1979 Page 2 of 2 3.
Inspect Remaining Piping The licensee is expected to inspect, as in Item 2 above, the remaining safety-related piping systems which were seismically analyzed and to report the results in accordance with the requirements for content and schedule as gi"en in Item 3 of the Bulletin.
4A.
Evaluate Noncomformances With regard to Item 3A for the Bulletin, the licensee is expected to include in the initial engineering judgement his justification for continued reactor operation.
For the analytical engineering evaluation, the licensee is expected to perform the evaluation by using the same analytical technique used in the seismic analysis or by an alternate, less complex techn:que provided that the licensee can show that it is conservative.
If either part of the evaluation shows that the system may not perform its intended function during a design basis earthquake, the licensee must promptly comply with applicable action statements and reporting requirements in the Technical Specifications.
4B.
Submit Nonconformance Evaluations The licensee is expected to submit evaluations of all nonconformances and, where the licensee concludes that the seismic analysis may not be conservative, submit schedules for reanalyris in accordance with Item 4B of the Bulletin or correct the noncomformances.
4C.
Correct Nonconformances If the licensee elects to correct nonconformances, the licensee is expected to submit schedules and work descriptions in accordance with Item 4C of the Bulletin.
4D.
Improve Qualtiy Assurance If noncomformances are identified, the licensee is expected to evaluate and improve quality assurance procedures to assure that future modifica-tions are handled efficiently.
In accordance with Item 4D of the Bulletin, the licensee is expected to revise design documents and seismic analyses in a timely manner.
The schedule for the action and reporting requirements given in the Bulletin as originally issued remains unchanged.
Approved by GA0 (R0072); clearance expires 7/31/80.
Approval was given under a blanket clearance specifically for generic problems.
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Supplement IE Bulletin No. 79-14 August 15, 1979 LISTING OF IE BULLETINS ISSUED IN LAST SIX MONTHS Bulletin Subject Date Issued Issued To No.79-01A Environmental Qualification 6/6/79 All Power Reactor of Class IE Equipment Facilities with an Operating License (0L) or Construction Permit (CP) 79-02 Pipe Support Base 3/8/79 All Power Reactor Plate Designs Using Facilities with an Concrete Expansion Operating License Anchor Bolts (OL) or Construction Permit (CP) 79-02 Pipe Support Base 6/21/79 All Power Reactor (Rev. 1)
Plate Designs Using Facilities with an Concrete Expansion Operating License Anchor Bolts (OL) or Construction Permit (CP) 79-03 Longitudinal Weld 3/12/79 All Power Reactor Defects In ASME SA-312 Facilities with an Type 304 Stainless Operating License Steel Pipe Spools (OL) or Construction Manufactured by Permit (CP)
Youngstown Welding and Engineering Company 79-04 Incorrect Weights 3/30/79 All Power Reactor for Swing Check Facilities with an Valves Manufactured Operating License by Velan Engineering (OL) or Construction Corporation Permit (CP) 79-05 Nuclear Incident at 4/1/79 All Power Reactor Three Mile Island Facilities with an Operating License (OL) or Construction Permit (CP)
Enclosure Page 1 of 4
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Supplement IE Eulletin No. 79-14 August 15, 1979 79-05A Nuclear Incident at 4/5/79 All Power Reactor Three Mile Island Facilities with an Operating License (OL) or Construction Permit (CP)79-05B Nuclear Incident at 4/21/79 All B&W Power Reactor Three Mile Island Facilities with an Operating License (0L) 79-06 Review of Operational 4/11/79 All Pressurized Water Errors and System Power Reactor Facilities Misalignments Identified Except B&W Facilities During The Three Mile Island Incident 79-06A Review of Operational 4/14/79 All Westinghouse PWR Errors and System Facilities with an Misaligaments Identified Operating License During ?.he Three Mile (OL)
Island Incident 79-06A Review of Operational 4/18/79 All Pressurized Water (Rev. 1)
Errors and System Mis-Power Reactor Facilities alignments Identified of Westinghouse Design During the Three Mile with an Operating License (OL)
Island Incident 79-06B Review of Operational 4/14/79 All Combustion Engineer-Errors and System ing PWR Facilities with Misalignments Identified an Operating License During The Three Mile (OL)
Island 79-07 Seismic Stress Analysis 4/14/79 All Power Reactor of Safety-Related Piping Facilities with an Operating License (0L) or Construction Permit (CP)
Enclosure Page 2 of 4 e
Supplement IE Bulletin No. 79-14 August 15, 1979 79-08 Events Relevant to BWR 4/14/79 All BWR Power Reactor Reactors Identified Facilities with an During Three Mile Island Operating License Incident (OL) or Construction Permit (CP) 79-09 Failures of GE Type AK-2 5/11/79 All Power Reactor Circuit Breaker in Safety Facilities with an Related Systems Operating License (OL) or Construction Permit (CP) 79-10 Requalification Training 5/11/79 All Power Reactor Program Statistics Facilities with an Operating License (0L) 79-11 Faulty Overcurrent Trip 5/22/79 All Power Reactor Device in Circuit Breakers Facilities with an for Engineered Safety Operating License (OL) or Systems a Construction Permit (CP) 79-12 Short Period Scrams at 5/31/79 All Power Reactor Facilities BWR Facilitic.s with an Operating License (0L) or a Construction Permit (CP) 79-13 Cracking In Feedwater 6/25/79 All PWRs with an Operating System Piping License (OL) for action.
All BWR with a Construction Permit (CP) for information 79-14 Seismic Analyses for 7/2/79 All Power Reactor facilities As-Built Safety-Related with an Operting License Piping System (OL) or a Construction Permit (CP) 79-15 Deep Draf t Pump 7/11/79 All Power Reactor Facilities Deficiencies with a Construction Permit and/or Operating License (OL) 79-16 Vital Area Access Controls 7/26/79 All Power Reactors with an Operating License (OL) or anticipating fuel loading prior to January 1981.
79-17 Pipe Cracks in Stagnant 7/26/79 All PWRs with Operating Borated Water Systems at License (OL)
PWR Plants Enclosure Page 3 of 4 lO U
Supplement IE Bd.: tin No. 79-14 August 15, 1979 79-18 Audibility Problems 8/6/79 All Power Reactor Encountered on Evacuation Facilities with an of Personnel from iligh-Operating License (OL)
Noise Areas 79-19 Packaging Low-Level 8/10/79 All Power and Research Radioactive Waste for Reactors with Operating Transport and Burial Licenses (OLs), fuel facilities except uranium mills, and certain materials licensees 79-20 Packaging Low-Level 8/10/79 Materials Licensees Radioactive Waste for who did not receive Transport and Burial Bulletin No. 79-19 79-21 Temperature Effects on 8/13/79 All PWR's with an Level Measurements Operating License (OL) for action.
All BWR's with a Construction Permit (CP) for info rmation Enclosure Page 4 of 4
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