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Forwards Request for Addl Info Re Util 890217 & 0310 Partial Responses to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment. Response Requested within 35 Days of Ltr Date
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 04/21/1989
From: Mcneil S
Office of Nuclear Reactor Regulation
To: Creel G
GL-88-14, TAC-71639, TAC-71640, NUDOCS 8905010058
Download: ML20245D580 (3)



April 21, 1989 Docket Nos. 50-317 '

DISTRIBUTION and 50-318 ' Docket file- NRC PDR PDI-l Rdg Local PDR SVarga BBoger Mr. G. C. Creel SMcNeil OGC Vice President - Nuclear Energy EJordan BGrimes Baltimore Gas and Electric Company ACRS (10) LTripp, RI Calvert Cliffs Nuclear Power Plant GEdison WLeFave MD Rtes. 2 & 4 RGallo, RI Post Office Box 1535 Lusby, Maryland 20657

Dear Mr. Creel:



(TAC NOS. 71639 AND 71640)

The NRC staff has completed its initial review of your submittals of February 17 and March 10, 1989 which provided a partial response to NRC Generic Letter 88-14, dated August 8, 1988, concerning possible adverse effects of instrument air system deficiencies en safety-related equipment.

Several questions and concerns arose, regarding your responses, during this initial staff review. These are detailed in the enclosed request for additional information.

Please provide the information as requested within 35 days of this letter's issuance date.

This request for information affects fewer than 10 respondents; therefore, OMB clearance is not required under Public Law 95-511.

Sincerely, Original signed by Scott Alexander McNeil, Project Manager Project Directorate I-1 Division of Reactor Projects I/II l


I As stated DFoi cc w/ enclosure:

See next page l;

/ l

[RAI 71639 & 71640]

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DATE : 4 / 28/89 :4 /Jf/89  : 4 /2i/89  :  :  :  :

OFFICIAL RECORD COPY 8905010059 DR 890421 p ADOCK 0500o317 PDC

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Mr. G. C. Creel L Raltimore Gas & Electric Company Calvert Cliffs Nuclear Power Plant

, cc:

l Mr. William T. Bowen, President Calvert County Board of Commissioners Prince Frederick, Maryland 20768 1

D. A. Brune, Esq.

General Counsel Baltimore Gas and Electric Company P. O. Box 1475 Raltimore, Maryland 21203 Mr. Jay E. S11 berg, Eso.

Shaw, Pittman, Potts and Trowbridge 1800 M Street, NW Washington, DC 20036 Mr. W. J. Lippold. General Supervisor Technical Services Engineering Calvert Cliffs Nuclear Power Plant MD Rts 2 & d, P. O. Rox 1535 Lusby, Maryland 20657 Resident Inspector c/o U.S. Nuclear Regulatory Comission P. O. Box 437 Lusby, Maryland 20657 Department of Natural Resources Energy Administration, Power Plant Siting Program ATTN: Mr. T. Magette Tawes State Office Building Annapolis, Maryland 21204 Regional Administrator, Region I U.S. Nuclear Regulatory Comission 475 Allendale Road King of Prussia, Pennsylvania 19406

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J REQUEST FOR ADDITIONAL INFORMATION BALTIMORE GAS AND ELECTRIC COMPANY CALVERT CLIFFS UNITS 1 AND 2 GENERIC LETTER 88-14 Generic Letter (GL) 88-14 requested the performance of a design and operations verification of the instrument air system. This verification was to include:

Verification that instrument air quality is consistent with manufacturer's recommendations for individual components served.

Verification that training is adequate for a loss of instrument air event.

Verification that the design of the entire instrument air system is in accordance with its intended function.

Verification by test that air-operated safety-related components will perform as expected in accordance with all design-basis events, including a loss of the normal instrument air system. GL 88-14 specified that this testing should be completed within 180 days but that it may be deferred until the next scheduled outage in order to avoid adverse system interactions.

In order to clarify your responses to GL 88-14, please provide the following information:

1. The actual instrument air quality test results previously mentioned in your March 10, 1989 letter, including particulate results, identification of any specific safety-related components for which your current instrument air quality test results do not meet their manufacturer's air quality recommendations, and a discussion of why no adverse effects are posed to the operability of these specific safety-related components.
2. A discussion of the corrective actions taken to improve the training given to both Plant Operators and Licensed Operators on the procedure for and the effects of a loss of instrument air, for the operator knowledge deficiencies noted in MRC Examination Report No. 50-317/87-19(OL) and 50-318/87-21(OL). This report identified the generic deficiency that all three Reactor Operators and all five Senior Reactor Operators that were examined "were weak with respect to the fail position of various valves after a loss of instrument air header pressure."
3. Details about the potential instrument air design concerns that were deleted.from your February 17, 1989 submittal, as was stipulated therein.
4. A more precise schedule for the specific outages during which tests of the air-operated safety-related components will be completed. The February 17, 1989 response has already led to confusion as Unit I underwent a planned outage in February-March 1989, which was af ter the expiration of the desired 180-day response time, yet the Unit I components were not tested.

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