ML18130A533
| ML18130A533 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  |
| Issue date: | 08/20/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Proffitt W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| References | |
| NUDOCS 7909070298 | |
| Download: ML18130A533 (8) | |
Text
e e a,,~?tf/111 l?i~s UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 Refer To:
..;.AUG 2 o 1979 Virginia Electric and Power Company ATTN:
W. L. Proffitt Senior Vice President, Power P. 0. Box 26666 Richmond, VA 23261 Gentlemen:
Enclosed is IE Bulletin No. 79-02, Revision 1, Supplement No. 1, which clarifies NRC positions on actions requested with regard to your power reactor facility(ies) with an operating license.
Should you have any questions regarding this Bulletin or the actions required by you, please contact this office.
Sincerely,
_, \\i \\--
<..:---:..:_-:-.. __ ~..,~ ~/
James P. O~t<.~il y Director
Enclosures:
- 1.
IE Bulletin No. 79-02, Revision No. 1 (Supplement No. 1)
- 2.
Listing of IE Bulletins Issued in Last Six Months
'7 909 0702 98
/
Virginia Elec(ric and Power Company cc w/encl:
W.R. Cartwright, Station Manager Post Office Box 402 Mineral, Virginia 23117 P. G. Perry Seni~r Resident Engineer Post Office Box 38 Mineral, Virginia 23117
.... ~ --*.
AUG 2. o 1979
e UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 August 20, 1979 SSINS:
6820 Accession No:
7908150164 IE Bulletin No. 79-02 Revision No. 1 (Supplement No. *1)
PIPE SUPPORT BASE PLATE DESIGNS USING CONCRETE EXPANSION ANCHOR BOLTS Description of Circumstances:
The supplement to IE Bulletin No. 79-02 is intended to establish_ criteria for the evaluation of interim acceptability of plant operation with less than the design factors of safety for piping supports due to as-built problems, under design, base plate flexibility, or anchor bolt deficiencies.
In the reviews for system operability of the Duane Arnold and Crystal River facilities, criteria have been developed by the NRC staff that defines pipe support operability. The criteria has been applied in lieu of other analysis or evalua-tion. Specifically, the licensees identified problems with pipe supports in which the original design factors of safety were not met but some lesser margin was available.
The design margins of four or five are intended to be final design and installation objectives but systems may be classed as operable on an interim basis with some lesser margin providing a program of restoration to at least the Bulletin factors of safety has been developed. Facilities which fall outside the operability criteria are considered to probably require a Technical Specifica-tion exception and will require review on a case by case basis.
Action to be Taken by Licensees:
For the following two cases, plant operation may continue or may begin:
- a.
For the support as a unit, the factor of safety compared to ulti-mate strengths is less than the original design but equal to or greater than two.
- b.
For the anchor bolts the factor of safety is equal to or greater than two and for the support steel the original design factor of safety com-pared to ultimate strengths is met.
The above criteria may be applied provided that the affected systems are up-graded to design margins of safety expeditiously for normally accessibile supports and by the next refueling for nonaccessible supports. Accessibility is as de-fined in Bulletin No. 79-14 where "normally accessible" refers to those areas of the plant which can be entered during reactor operation.
IE Bulletin No. 79-02, Revision No. 1 (Supplement No. 1) e Page 2 of 2 August 20, 1979
- 1.
Any support not satisiying the criteria should be classed as inoperable and the Technical Specification action statement met unless it can be shown that the system can function in a design basis seismic event without the support.
- 2.
Repairs to supports should result in return to the design factor of safety.
- 3.
Operations may be continued while repairs to upgrade the system from a.factor of safety equal to or greater than two with respect to design loads are performed.
Consideration must be given to the effect of the repair process on support function and system operability.
In other words the time the support is not functional should be limited to T.S. action statement times or the support must be determined not to cause the system to be unable to perform its function in a seismic event.
The licensee should also exercise care not to take several supports on a given system out of service at the same time or cause both trains of one safeguards system to be made inoper-able at the same time.
Control over workmen on safety related systems during plant operation requires a high degree of control by the licensee.
- 4.
There are no special reporting requirements for this supplement to the Bulletin; however, the reporting requirements as set forth in the regula-tions and licenses must be met.
~
I
IE Bulletin No. 79-02 Revision 1, Supplement No. 1 August 20, 1979 Bulletin No.
79-18 79-17 79-16 79-15 (Supp. 1) 79-15 79-14 (Correc-tion) 79-14 (Rev. 1) 79-14 79-13 LISTING OF IE BULLETINS ISSUED IN LAST SIX MONTHS Subject Date Issued 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 Seismic Analyses for 7/18/79 As-Built Safety-Related Piping System Seismic Analyses for 7/2/79 As-Built Safety-Related Piping System Cracking in Feedwater 6/25/79 System Piping Enclosure Page 1 of 4 Issued To 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 All Power Reactor Facilities with an OL or a CP All Power Reactor facilities with an OL or a CP All PWRs with an OL for action. All BWRs with a CP for information
e IE Bulletin No. 79-02 Revision 1, Supplement No. 1 August 20, 1979 Bulletin No.
79-12 79-11 79-10 79-09 79-08 79-07 79-06C 79-06B 79-06A (Rev 1)79-06A LISTING OF IE BULLETINS ISSUED IN LAST SIX MONTHS Subject Date Issued 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 Review of Operational 4/14/79 Errors and System Mis-alignments Identified During the Three Mile Island Incident Review of Operational 4/18/79 Errors and System Mis-alignments Identified During the Three M1le Island Incident Review of Operational 4/14/79 Errors and System Mis-alignments Id~ntified During the Three Mile Island Incident Enclosure
- Page 2 of 4 Issued To All GE BWR Facilities with an OL All Power Reactor Facilities with an OL or a CP All Power Reactor Facilities with an OL All Power Reactor Facilities with an OL or CP All BWR Power Reactor Facilities with an OL All Power Reactor Facilities with an OL or CP To all PWR Power Reactor Facilities with an OL 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 OL All Pressurized Water Power Reactor Facilities of Westinghouse Design with an OL
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IE Bulletin No. 79-02 Revision 1, Supplement No. 1 August 20, 1979 LISTING OF IE BULLETINS ISSUED IN LAST SIX MONTHS Bulletin Subject Date Issued No.
79-06 Review of Operational 4/11/79 Errors and System Mis-alignments Identified During the Three Mile Island "Incident 79-0SC Nuclear Incident at Three 7 /26/79 Mile Island - Supplement 79-0SB Nuclear Incident at 4/21/79 Three Mile Island 79-0SA Nuclear Incident at 4/5/79 Three Mile Island 79-05 Nuclear Incident at 4/1/79 Three Mile Island 79-04 Incorrect Weights for 3/30/79 Swing Check Valves Manufac'tured by Velan Engineering Corporation 79-03 Longitudinal Welds Defects 3/12/79 In ASME SA-312 Type 304 Stainless Steel Pipe Spools Manufactured by Youngstown Welding and Engineering Co.
79-02 Pipe Support Base Plate 6/21/79 (Rev. 1)
Designs Using Concrete Expansion Anchor Bolts 79-02 Pipe Support Base Plate 3/8/79 Designs Using Concrete Using Concrete Expansion Anchor Bolts I
Enclosure Page 3 of 4 Issued To All Pressurized.Water Power Reactors with-an OL except B&W facilities To all PWR Power Reactor Facilities with an OL All B&W Power Reactor Facilities with an 01 All B&W Power Reactor Facilities with an 01 All Power Reactor Facilities with an 01 and CP All Power Reactor Facilities with an OL or CP All Power Reactor Facilities with an 01 or CP All Power Reactor Facilities with an 01 or a CP All Power Reactor Facilities with an 01 or a CP
IE Bulletin No. 79-02 Revision 1, Supplement No. 1 August 20, 1979 LISTING OF IE BULLETINS ISSUED IN LAST SIX MONTHS Bulletin Subject Date Issued No.
79-0lA Environmental Qualification 6/6/79 of Class lE Equipment (Deficiencies in the Envi-ronmental Qualification of ASCO Solenoid Valves) 79-01 Environmental Qualification 2/28/79 (Correc-of Class IE Equipment tion)
(Deficiencies in the Envi-ronmental Qualification of ASCO Solenoid Valves) 79-01 Environmental Qualification 2/8/79 of Class IE Equipment (Deficiencies in the Envi-ronmental Qualification of ASCO Solenoid Valves)78-12B Atypical Weld Material 3/19/79 in Reactor Pressure Vessel Welds Enclosure Page 4 of 4 Issued To All Power Reactor Facilities w{th an OL or CP All Power Reactor Facilities with an OL or CP All Power Reactor Facilities with an OL or CP All Power Reactor Facilities with an OL or CP