ML19207B770
| ML19207B770 | |
| Person / Time | |
|---|---|
| Issue date: | 08/16/1979 |
| From: | Pappas H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Wright G ILLINOIS, STATE OF |
| References | |
| NUDOCS 7909050249 | |
| Download: ML19207B770 (2) | |
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GLEN ELLYN. ILLINols 60137 AUG1 6 19I9 State of Illinois Department of Public Health ATTN:
Mr. Gary N. Wright, Chief Division of Nuclear Safety 535 West Jefferson Street Springfield, IL 62761 Gentlemen:
The enclosed Supplement IE Bulletin No. 79-14 titled " Seismic Analysis For As-Built Safety-Related Piping Systems" was sent to the following licensees on August 15, 1979:
American Electric Power Service Corporation Indiana and Michigan Power Company D. C. Cook 1, 2 (50-315, 50-316)
Cincinnati Gas & Electric Company Zimmer (50-358)
Cleveland Electric Illuminating Company Perry 1, 2 (50-440, 50-441)
Commonwealth Edison Company Braidwood 1, 2 (50-456, 50-457)
Byron 1, 2 (50-454, 50-455)
Dresden 1, 2, 3 (50-10, 50-237, 50-249)
La Salle 1, 2 (50-373, 50-374)
Quad-Cities 1, 2 (50-254, 50-265)
Zion 1, 2 (50-295, 50-304)
Consumers Power Company Big Rock Point (50-155)
Midland 1, 2 (50-329, 50-330)
Palisades (50-255)
Dairyland Power Cooperative LACBWR (50-409)
Detroit Edison Company Fermi 2 (50-341)
Illinois Power Company Clinton 1, 2 (50-461, 50-462) 790905ovM s no7a_
e State of Illinois AUG 161971 Iowa Electric Light & Power Company Duane Arnold (50-331)
Northern Indiana Public Service Company Bailly (50-367)
Northern States Power Company Monticello (50-263)
Prairie Island 1, 2 (50-282, 50-306)
Tyrone Energy Park 1 (50-484)
Ohio Edison Company Erie I, 2 (Pre-CPP)
Public Service of Indiana Marble Hill 1, 2 (50-546, 50-547)
Toledo Edison Company Davis-Besse 1 (50-346)
Union Electric Company Callaway 1, 2 (50-483, 50-486)
Wisconsin Electric Power Company Point Beach 1, 2 (50-266, 50-301)
Wisconsin Public Service Corporation Kewaunee (50-305)
Sincerely, 4.j'!r.. % ', / p f ) f ? f a /
i Helen Pappas, Chief Administrative Branch
Enclosure:
Supplement IE Bulletin No. 79-14 cc w/ encl:
Mr. D. W. Kane, Sargent & Lundy Central Files Reproduction Unit NRC 20b Local PDR NSIC TIC o, s.m..,
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I UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
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Supplement IE Bulletin No. 79-14 SEISMIC ANALYSIS FOR AS-BUILT SAFETY-RELATED PIPING SYSTEMS Discription of Circumstances:
IE Bulletin No. 79-14 was issued on July 2, 1979 and revised on July 18, 1979.
The bulletin requested licensees to take certain actions to verify that seismic analyses are applicable to as-built plants. This supplement to the bulletin provides additional 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 inspectons, the licensee is expected to use measuring techniques of sufficient accuracy to demonstrate that acceptance criteria are met.
Where inspection 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 (wituin 30 days).
Where either phase of the evaluation shows that system operability is in jeopardy, the licensee is expected to meet the applicable 4-technical specification action statement and complete the inspections N
required by Item 2 and 3 of the Bulletin as soon as possible.
The licensee
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must report the results of these inspections in accordande with the require-ments for content and schedule as given in Item 2 and 3 o_f the Bulletin.
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Supplement IE Bulletin No. 79-14 Page 2 of 2 August 15, 1979 e
, 3.
Inspect Remaining Piping The licensee is expected to inspect, as in Item 2 above, The remaining safety-related piping systems which were seismically anal [ zed and to report the results in accordance with the requirements for content and jr schedule as given in Item 3 of the Bulletin.
A.
Evaluate Noncomfonnances 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 technique 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 reanalysis 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.
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f@e schedule for the action and reporting requirements given iq the Bulletin jas originally issued remains unchanged.
h Approved by GAO, B180225 (R0072), clearance expires 7/31/80.
4pproval was given under a blanket clearance specifically for identified generic $roblems.
Enclosure:
Listing of IE Bulletins Issued in Last 6 Months
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1 LISTING OF IE BULLETINS ISSUED IN LAST SIX MONTHS i
Bulletin Subject Date Issued Issued To No.
79-18 Audibility Problems Encount-8/7/79 All ower Reactor ered on Evaluation of Per-facsiities with an M
sonnel From High Noise Areas OL
-17 Pipe Cracks in Stagnant 7/26/79 All PWR's with Borated Water Systems at operating license PWR ?lants 79-16 Vital Area Access Controls 7/26/79 All Holders of and applicants for Power Reactor Operating Licenses who anticipate loading fue prior to 1981 79-15 Deep Draft Pump 7/11/79 All Power Reactor Deficiencies Licensees with a CP and/or OL 79-14 Seismic Analyses for 6/2/79 All Power Reactor As-Built Safety-Related facilities with an Piping System OL or a CP 79-13 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 CE 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 Systems
+79-10 Pequalification Training 5/11/79 All Power Reactor O
Program Statistics Facilities with an OL U
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~ 9-09 Failures of GE Type AK-2 4/17/79 All' Power Reactor
'1 Circuit Breaker in Safety Facilities with an Related Systems OL or CP 79-08 Events Relevant to BWR 4/14/79 All BWR Power Reactor Reactors Identified During Facilities with an OL Three Mile Island Incident T
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Supplement IE Bulletin No. 79-14 Enclosure August 15, 1979 Page 2 of 3 79-07 Seismic Stress Analysis
'4/14/79 All, Power Reactor of Safety-Related Piping Facq4itieswithan OL ar CP t
1579-05C&O6C Nuclear Incident at Three 7/26/79 To all PWR Power l{g Mile Island - Supplement Reactor Facilities with an OL 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 4/18/79 All Pressurized Water (Rev 1)
Errors and System Mis-Power Reactor Facilities alignments Identified of Westinghouse Design During the Three Mile with an OL Island Incident 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
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Supplement IE Bulletin No. 79-14 Enclosure August 15, 1979 Page 3 of 3 LISTING OF IE BULLETINS ISSUED IN LAST SIX MONTHS Bulletin Subject Date Issued Issied To No.
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%79-05B Nuclear Incident at 5/21/79 All B&W Power Reactor 6kg Three Mile Island Facilities with an OL 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 79-04 Incorrect Weights for 3/30/79 All Power Reactor Swing Check Valves Facilities with an Manufactured by Velan OL or CP Engineering Corporation 78-12B Atypical Weld Material 3/19/79 All Power Reactor in Reactor Pressure Facilities with an Vessel Welds OL or CP 79-03 Longitudinal Welds Defects 3/12/79 All Power Reactor In ASME GA-312 Type 304 Facilities with an Stainless Steel Pipe Spools OL or CP Manufactured by Youngrtown Welding and Engineering Co.79-01A Environmental Qualification 6/6/79 All Power Reactor of Class 1E Equipment Facilities with an (Deficiencies in the Envi-OL or CP roamental Qualification of ASCO Solenoid Valves)
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