ML18043B079
| ML18043B079 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 08/13/1979 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Dewitt R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| NUDOCS 7910090168 | |
| Download: ML18043B079 (6) | |
Text
Docket No. 50-255 Consumers Power Company ATTN:
Mr. R. B. DeWitt Vice President Nuclear Operations 212 West Michigan Avenue Jackson, MI 49201 Gentlemen:
Enclosed is IE Bulletin No. 79-21 which requires action by you with regard to your PWR power reactor facility with an operating license.
Should you have any questions regarding this Bulletin or the actions required by you, please contact this office.
Enclosures:
- 1.
- 2.
List of IE Bulletins Issued in the Last 6 Months cc w/encls:
Mr. J. G. Lewis, Manager Central Files Director, NRR/DPM Director, NRR/DOR PDR Local PDR NSIC TIC Ronald Callen, Michigan Public Service Commission Myron M. Cherry, Chicago RIII Heis~n/bk 8/13/79 RIII G~
KepJ'ler-.
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Sincerely, James G. Keppler Director 7910090
UNITED STATES e
Accession No:
7908090193 SSINS No:
6820 NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D. C..20555 August 13, 1979 IE Bulletin No. 79-21 TEMPERATURE EFFECTS ON LEVEL MEASUREMENTS Description of Circumstances:
On June 22, 1979, Westinghouse Electric Corporation reported, to NRC, a potential substantial safety hazard under 10 CFR 21.
The report, Enclosure No. 1, addresses the effect of increased containment temperature on the reference leg water column and the resultant effect on the indicated steam generator water level. This effect would cause the indicated steam generator level to be higher than the actual level and could delay or prevent protection signals and could, also, provide erroneous information during post-accident monitoring.
Enclosure No. 1 addresses only a Westinghouse steam generator reference leg water column; however, safety related liquid level measuring systems utilized on other steam generators and reactor coolant systems could be affected in a similar manner.
Act ions To Be Taken By Licensees:
For all pressurized water power reactor facilities with an operating license:*
- 1.
Review the liquid level measuring systems within containment to determine if the signals are used to initiate safety actions or are used to provide post-accident monitoring information.
Provide a description of systems that are so employed; a description of the type of reference leg shall be included, i.e., open column or sealed reference leg.
- 2.
On those systems described in Item 1 above, evaluate the effect of post-accident ambient temperatures on the indicated water level to determine any change in indicated level relative to actual water level. This evaluation must include other sources of error including the effects of varying fluid pressure and flashing ~f reference leg to steam on the water level measurements.
The results of this evaluation should be presented in a tabular form similar to Tables 1 and 2 of Enclosure 1.
- 3. Review all safety and control setpoints derived from level signals to verify that the setpoints will initiate the action required by the plant safety analyses throughout the range of ambient temperatures encountered by the instrumentation, including accident temperatures.
Provide a listing of these setpoints.
- Boiling water reactors have been requested by a July generic letter from the NRC to provide similar information.
IE Bulletin ~o. 79-21 August 13, 1979 Page 2 of 2 If the above reviews and evaluations require a revision of setpoints to ensure safe operation, provide a description of the corrective action and the date the action was completed.
If any corrective action is temporaryr submit a description of the proposed final corrective action and a timetable for implementation.
- 4.
Review and revise, as necessary, emergency procedures to include specific information obtained from the review and evaluation of Items 1, 2 and 3 to ensure that the operators are instructed on the potential for and magnitude of erroneous level signals. All tables, curves, or correction factors that would be applied to post-accident monitors should be readily available to the operator. If revisions to procedures are required, provide a completion date for the revisions and a completion date for operator training on the revisions.
A report of the above actions shall be submitted within 30 days of the receipt of this Bulletin.
Reports should be submitted to the Director of the appropriate NRC Regional Office and a copy should be forwarded to the NRC Office of Inspection and Enforcement, Division of Reactor Operations Inspection, Washington, D. C.
20555, I For boiling water reactors with an operating license and all power reactors with a construction permit, this Bulletin is for information purposes and no written response is required.
Approved by GAO, B180225 (R0072); clearance expires 7/31/80.
Approval was given under a blanket clearance specifically for identified generic problems.
Enclosure:
Memo Westinghouse Electric Corp.
to Victor Stello dated June 22, 1979
IE Bulletin No. 79-21 August 13, 1979 Bulletin No.
79-20 79-19 79-18 79-17 79-16 79-15 79-14 79-13 79-02
(~ev. 1) 79-12 LISTING OF IE BULLETINS ISSUED IN LAST SIX MONTHS Subject Date *Issued 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 Evacuation Pipe Cracks in Stagnant 7/26/79 Borated Water Systems at PWR Plants Vital Area Access Controls 7/26/79 Deep Draft Pump 7/11/79 Deficiencies
- Seismic Analyses for 6/2/79 As-Built Safety-Related Piping System Cracking In Feedwater 6/25/79 System Piping Pipe Support Base Plate 6/21/79 Designs Using Concrete Expansion Anchor Bolts Short Period Scrams at 5/31/79 BWR Facilities
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Enclosure Page 1 of 3 Issued"To 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 Power Reactor Facilities with an Operating License 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 facilities with an OL or a CP All PWRs with an OL for action. All BWRs with a CP for information.
All Power Reactor Facilities with an OL or a CP All GE BWR Facilities with an OL
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IE Bulletin No. 79-21 Enclosure August 13, 1979 Page 2 of 3 LISTING OF IE BULLETINS ISSUED IN LAST SIX MONTHS Bulletin Subject Date Issued Issued.To No.
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 Requalification Training.
5/11/79 All Power Reactor Program Statistics Facilities with an OL 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 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 79-0SC&06C Nuclear Incident at Three 7/26/79 To all PWR Power Mile Island ~ Supplement Reactor Facilities with an OL 79-068 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 7°9-06A 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
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IE Bulletin No. 79-21 Enclosure August 13, 1979 Page 3 of 3 LISTING OF IE BULLETINS ISSUED IN LAST SIX MONTHS Bulletin Subject Date *Issued Issued ~To No.
79-06 Review of Operational 4/11/79 All Pressurized Water Errors and System ~is-Power Reactors with an alignments Identified OL except B&W facilities During the Three Mile Island Incident 79-058 Nuclear Incident at 5/21/79 All B&W Power Reactor 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 78-128 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 SA-312 Type 304 Facilities with an Stainless Steel Pipe Spools
- oL or CP Manufactured by Youngstown Welding and Engineering Co.
79-0lA Environmental Qualification 6/6/79 All Power Reactor of Class lE Equipment Facilities with an (Deficiencies in the Envi-OL or CP ronmental Qualification of ASCO Solenoid Valves)
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