ML18135A131
| ML18135A131 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  |
| Issue date: | 09/07/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Proffitt W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| References | |
| NUDOCS 7909210387 | |
| Download: ML18135A131 (8) | |
Text
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e UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II
. '101 MARIETIA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 In Reply Refer RII:JPO 50-338, 50-404, 50-280, 50-339 5Q-405 5fi..281 To:
Virginia Electric and Power Company Attn:
W. L. Proffitt Senior Vice President,.
Power P.O. Box 26666 Richmond, Virginia 23261 Gentlemen:
- sfp ?
1979 The enclosed supplement to Bulletin No. 79-14 is forwarded to you to provide added guidance on the intent of the Bulle~in. If you desire additional information regarding this matter, please contact this office.
Sincerely,
-*-* *---****-**---~*,
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Enclosures:
- 1.
Supplement 2 to IE Bulletin No. 79-14
- 2.
List of IE Bulletins Issued in the Last Six Months James P. O'Reilly Director
_J
Virginia Electric and Power Company cc w/encl:
W.R. Cartwright, Station Manager Post Office Box 402 Mineral, Virginia 23117 P. G. ~rry Senior Resident Engineer Post Office Box 38 Mineral, Virginia 23117 W. L. Stewart, Manager Post Office Box 315 Surry, Virginia 23883 *---- -
e SSINS:
6820 Accesstion No.: 7908220109 UNITED STATES NUCLEAR REGULATO~Y COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 September 7, 1979 IE Bulletin No. 79-14 Supplement 2 SEISMIC ANALYSIS FOR AS-BUILT SAFETY-RELATED 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 configuratiop 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.
I e
e 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 details, i.e. attachment welds, saddles, support configuration, etc.
areas, the presence of thermal insulation may result in unacceptably uncertainties for determination of the location of pipe supports.
Where thermal insulation obstructs inspection of support details, the support In some large insulation should be removed for inspection of a minimum of 10% of the obstructed pipe supports in both Item 2 and 3 inspections.
In.the Item 3 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 revi~w.
Schedule The schedule for the action and reporting requirements given in the Bulletin as originally issued remains unchanged.
e IE Bulletin No. 79-14, Supplement 2 September 7, 1979 Bulletin No.
79-22 \\
79-21 79-20 79-19 79-18 79-17 79-16 79-15 (Supp. 1) 79-15 79-14 (Correc-tion)
LISTING OF IE BULLETINS ISSUED IN LAST SIX MONTHS Subject Date Issued Possible Leakage of 9-/5/79 Tubes of Tritium Gas Used in Timepieces for Luminosity Temperature Effects 8/13/79 on Level Measurements Packaging Low-Level 8/10/79 Radioactive Waste for Transport and Burial Packaging Low-Level 8/10/79 Radioactive Waste for Transport and Burial Audibility Problems 8/7/79 Encountered on Evacua-tion of Personnel from High-Noise Areas Pipe Cracks in Stagnant 7/26/79 Borated Water Systems at PWR Plants Vital Area Access Controls 7/26/79 Deep Draft Pump 7/18/79 Deficiencies Deep Draft Pump 7/11/79 Deficiencies Seismic Analyses for 7/27/79 As-Built Safety-Related Piping System e
Enclosure Page 1 of 4 Issued To Each Licensee who Receives Tubes of Tritium Gas in Timepieces for Luminosity All PWRs with an operating license All Materials Licensees who did not receive Bulletin No. 79-19 All Power and Research Reactors with OLs, fuel facilities except uranium mills, and certain materials licensees All OL's for action All CP's for information All PWR' s with operating license All Holders of and applicants for Power Reactor Operating Licenses who anticipate loading fuel prior to 1981 All Power Reactor Licensees with a CP and/or OL All Power Reactor Licensees with a CP and/or OL All Power Reactor Facilities with an OL or a CP
IE Bulletin No. 79-14, Supplement 2 September 7, 1979 Bulletin No.
79-14 '
(Supp. 2) 79-14 (Rev. 1) 79-14 79-13 (Rev. 1) 79-13 79-12 79-11 79-10 '
79-09 79-08 79-07 79-:-06C LISTING OF IE BULLETINS ISSUED IN LAST SIX MONTHS Subject Seismic Analyses for As-Built Safety-Related Piping System Seismic Analyses for As-Built Safety-Related Piping System Seismic Analyses for As-Built Safety-Related Piping System Cracking in Feedwater System Piping Cracking in Feedwater System Piping Date Issued 9/7/79 7/18/79 7 /2/79 8/30/79 6/25/79 Short Period Scrams at 5/31/79 BWR Facilities Faulty Overcurrent Trip 5/22/79 Device in Circuit Breakers for Engineered Safety Systems Requalification Training 5/11/79 Program Statistics Failures of GE Type AK-2 4/17/79 Circuit Breaker in Safety Related Systems Events Relevant to BWR 4/14/79 Reactors Identified During Three Mile Island Incident Seismic Stress Analysis 4/14/79 of Safety-Related Piping Nuclear Incident at Three 7/26/79 Mile Island - Supplement e
Enclosure Page 2 of 4 Issued To All Power Reactor facilities with an 01 or a CP All Power Reactor' Facilities with an OL or a CP All Pqwer Reactor facilities with an OL or a CP All PWR's with an operating license All PWRs with an 01 for action. All BWRs with a CP for information All GE BWR Facilities with an 01 All Power Reactor Facilities with an 01 or a CP All Power Reactor Facilities with an 01 All Power Reactor Facilities with an 01 or CP All BWR Power Reactor Facilities with an 01 All *Power Reactor Facilities with an OL or CP To all PWR Power Reactor Facilities w:j..th ~n O~
1*
i e
IE Bulletin No. 79-14, Supplement 2 September 7, 1979 Bulletin No.
\\
79-06B
- 79-06A (Rev. 1)79-06A 79-06 79-05C 79-05B 79-05A 79-05 LISTING OF IE BULLETINS ISSUED IN.J.AST SIX MONTHS Subject Review of Operational Errors and System Mis-alignments Identified During the Three Mile Island Incident Review of Operational Errors and System Mis-alignments Identified During the Three Mile Island Incident Review of Operational Errors and System Mis-alignments Identified During the Three Mile Island Incident Review of Operational Errors and System Mis-alignments Identified During the Three Mile Island Incident Nuclear Incident at Three Mile Island - Supplement Nuclear Incident at Three Mile Island Nuclear Incident at Three Mile Island Nuclear Incident at Three Mile Island
)
Date Issued 4/14/79 4/18/79 4/14/79 4/11/79 7/26/79 4/21/79 4/5/79 4/1/79 e
Enclosure Page 3 of 4 Issued To All Combustion Engineer-ing Designed Pressurized Water Power Reactor Facilities with an Operating License All Pressurized Water Power Reactor Facilities of Westinghouse Design with an 01 All Pressurized Water Power Reactor Facilities of Westinghouse Design with an 01 All Pressurized Water Power Reactors with an 01 except B&W facilities To all PWR Power Reactor Facilities with an 01 All B&W Power Reactor Facilities with an 01 All B&W Power Reactor Facilities with an 01 All Power Reactor Facilities with an OL and CP
e IE Bulletin No. 79-14, Supplement 2 September 7, 1979 Bulletin No.
79-02 '
(Rev. 1Y (Supp. 1) 79-02 (Rev. 1) 79-0lA LISTING OF IE BULLETINS ISSUED IN LAST SIX MONTHS Subject Date Issued Pipe Support Base Plate 8/20/79 Designs Using Concrete Expansion Anchor Bolts Pipe Support Base Plate 6/21/79 Designs Using Concrete Expansion Anchor Bolts Environmental Qualification 6/6/79 of Class lE Equipment (Deficiencies in the Envi-ronmental Qualification of ASCO Solenoid Valves) e Enclosure Page 4 of 4 Issued To All Power Reactor Facilities with an OL or a CP All Power Reactor Facilities with an OL or a CP All Power Reactor Facilities with an OL or CP