ML19256F430
| ML19256F430 | |
| Person / Time | |
|---|---|
| Issue date: | 11/19/1979 |
| From: | Grimes B Office of Nuclear Reactor Regulation |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-CR-0660, RTR-NUREG-CR-660 NUDOCS 7912190133 | |
| Download: ML19256F430 (8) | |
Text
(R 8(I Io UNITED STATES g
NUCLEAR REGULATORY COMMISSION o
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WASHINGTON, D. C. 20555
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NOV 191979 MEMORANDUM FOR: Darrell G. Eisenhut, Acting Director Division of Operating Reactors FROM:
Brian K. Grimes, Acting Assistant Director for Syster.;. Engineering Division of Operating Reactors
SUBJECT:
IMPLEMENTATION OF RECOMMENDATIONS CONTAINED IN NUREG/CR 0660 REPORT, ENHANCEMENT OF ONSITE EMERGENCY DIESEL GENERATOR RELIABILITY Enclosed is a draft memo to OR Branches and DPM, and a draft generic letter requesting implementation of the recommendations of the subject document.
This action is a part of B-56.
In addition, it seems appropriate action at this time considering the results and activities of the piant analyses and activities of the Probabilistic Analyses Staff (RES) associated with their work on A-44, " Station Blackout."
Enclosed also is the estimated manpower necessary to complete this action. At S. Hanauer's request, Gary Zech is attempting to establish the status, schedule, funding and manpower to complete B-56.
Do you concur with the attached and the use of an outside contractor?
/:a Brian K. Grimes, Acting Assistant Dimetor for Systems Engineering Division of Operating Reactors Enclosures :
As stated
Contact:
F. Clemenson, X27546 1620 077 I33 7912100
- 1. s F Darrell G. Eisenhut NOV 191979 cc w/ enclosures:
F. Rosa A. Ungaro E. Adensam G. Lainas R. Vollmer F. Clemenson D. Tondi R. Tedesco
. Q..
1624 278 9
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e DRAFT MEMO MEMORANDUM FOR:
A. Schwencer, Chief, Operating Reactors Branch #1, D0R D. Ziemann, Chief, Operating Reactors Branch #2, D0R T. Ippolito, Chief, Operating Reactors Branch #3, D0R R. Reid, Chief, Operating Reactors Branch #4, DOR D. Yassallo, Assistant Director for Project Management S. Varga, Chief, Light Water Reactors Branch #4, DPM FROM:
Richard H. Vollmer, Acting Assistant Director for Systematic Evaluation Program, D0R Brian.K. Grimes, Acting Assistant Director for Systems Engineering, D0R William P. Gamill, Acting Assistant Dimctor for Operating Reactor Projects. D0R
SUBJECT:
IMPLEMENTATION OF RECOMMENDATIONS CONTAINED IN NUREG/CR 0660 REPORT, ENHANCEMENT OF ONSITE EMERGENCY DIESEL GENERATOR RELIABILITY The emergency onsite diesel generator reliability has proven to be less than anticipated.
Due to the importance in having onsite emergency AC power during certain postulated situations, a generic task action plan, B-56, " Diesel Reliability," has been established As part of this effort NRC/ DOR awarded a contract to the University of Dayton Research Insitute to perfonn a generic study and to develop a series of recommendations which would significantly improve the reliability of the units.
This study and its recomend-ations are presented in NUREG/CR 0660, " Enhancement of Onsite Emergency Diesel Generator Reliability."
In addition, there have been recent preliminary studies by the Probabilistic Analysis Staff that confirms the lower than anticipated reliability at least for some plants. Therefore, it is proposed that the enclosed generic letter, requesting responses to the report's recommendations, be sent to all light water operating power reactors, all construction permit holders and all applicants for construction permits. The attached Enclosure 1 gives some background information on this particular concern, Enclosure 2 is the Plant Systems Branch estimate of the manyears required to complete their portion of the program on the operating plants, and Enclosure 3 is the proposed sample generic letter requesting a response to the recommendations contained in NUREG/CR 0660.
(
- Upon receipt of the proposed signed original of the generic letter to be sent to the licensees, the AD/0RP (Shirley Sheppard), Mr. D.
Vassallo's representative (Margaret Service), and S. Varga's repre-sentative (J. Stolz) will send their respective plants - operating plants, construction permit holders, and applicants for construction permits the generic letter requesting a response to each recommendation contained in NUREG/CR 0660. The responsible individual for each plant will be informed that the letters have actually been dispatched by receiving a copy of the letter sent to their assigned facility.
By copy of this letter.the above individuals are being informed of our action.
Richard H. Vollmer, Acting Assistant Brian K. Grimes, Acting Assistant Director for Systematic Evaluation Cirector for Systems Engineering Program Division of Operating Reactors Division of Operating Reactors William P. Gammill, Acting Assistant Director for Operating Reactor Projects Division of Operating Reactors Enclosures :
As stated
Contact:
F. Clemenson, X27546 cc w/ enclosures:
D. Eisenhut R. Tedesco R. Vollmer W. Gammill D. Vassallo S. Varga G. Lainas W. Russell D. Tondi S. Hcnauer F. Rosa V. Thomas V. Stello E. Jordan 1/ ?ff (;
'7 A. Ungaro E. Adensam D. Crutchfield M. Fletcher m
BACKGROUND INFORMATION The onsite emergency diesel generator units operating experience has proven to be lesr, reliable than anticipated. As the first step in igroving the ' situation, NRC/ DOR awarded a contract to the University of Dayton Research Institute (U of D) to perform a comprehensive review of diesel generator {DG) operating experience, and DG maintenance plus a comparattve evaluation of their findings with respe t to the DG manufacturers' recommendations. Additionally, U of D was to identify the more significant causes for the unreliability, categorize the causes in accordance with their relative importance and develop a set of recommendations which, if implemented, would upgrade the reliability of the onsite emergency diesel generator units.
Their final report, NUREG/CR 0660, " Enhancement of Onsite Emergency Diesel Generator Reliability,"
containing the above, was published February 1979 and sent to all light water operating plants, construction permit holders and applicants for construction permits.
JRC has reviewed and evaluated NUREG/CR 0660 and concurs that implementing the mport's recommendations would significantly upgrade the reliability of the DG units.
Further, due to tiie possible undesirable consequences following certain postulated conditions, we propose to send the attached generic letter to all light water operating reactors, all construction permit holders and all applicants for construction permits. The generic letter requests that the recipients develop responses to each of the recommendations. The responses are to demonstrate that (a) each of the recommendations are presently being met, (b) each of the recommendations will be met, including the schedule if implemen-tation of the recomendation, (c) what they currently are doing is the equivalent or exceeds the intent of the recomendation, or (d) a detailed basis exists as to why the particular recomendation is not applicable to their facility.
1620 4 1 4
D0R Manyear Estimate to complete the Plant Systems Branch portion of Task Action Plan B-56 (including SEP Plants).
I.
POSSIBLE TECHNICAL OUTSIDE ASSISTANCE a.
Review responses to generic letter.
1.0 MY b.
Plant visit to facilities, to evaluate those plant unique features that in a practical sense limit their ability to fully comply with the reconmendations of NUREG/CR 0660.
0.5 MY c.
Prepare the Safety Evaluation Report for each facility.
0.5 MY II. Plant Systems Branch - D0R Management of the program.
0.5 MY TOTAL PSB/ DOR MANYEARS 2.5 1620lj82
d<
SAMPLE GENERIC LETTER To All Light Water Power Reactor Licensees, Construction Permit Holders and Applicants for Construction Pennits Gentlemen:
The diesel generator operating experience has proven to be less reliable than anticipated. Therefore, the University of Dayton Research Institute (U of D), under contract with NRC/ DOR, performed a generic study to identify the more significant causes for this unreliability and to categorize the causes in their relative order of importance. Briefly, the significant identified causes in the final report NUREG/CR 0660, " Enhancement of Onsite Emergency Diesel Generator Reliability," are listed below.
I.
Most Significant Problems a) Moisture in the Air Starting Systems b)
Dust and Dirt in Diesel Generator Compartments c) Turbocharger Gear Drive Changeover d)
Personnel Training II.
Significant Problems a) Length of Pre-lube Time b) Testing, Test Loading & Preventative Maintenance c)
Improve the Identification of Root Causes of Failures III. Additional Problems a)
D.G. Room Ventilation and Combustion Air Intake Systems b)
Fuel Storage and Handling c) High Temperature Insulation for Generator Overload Conditions d)
Engine Cooling Water Temperature Control e)
Concrete Dust Control f) Viu"ation of Instruments and Controls 1620 083
o...
.Section V of the report concluded with a set of recommendations of the measures required to upgrade the reliability of the onsite emergency diesel generator units. The final report was published on February 1979, and sent to all light water reactor operating reactors, all construction pennit holders and applicants for construction permits. The cover letter accompanying the report inidcated NRC was in the process of reviewing and evaluating the report. NRC has completed its review of NUREG/CR 0660, " Enhancement of Onsite Emergency Diesel Generator Reliability," and concurs with U of D findings that the recom-mended corrective actions would significantly upgrade the reliability of the units.
Therefore, we are requesting that all light water operating reactors, all construction pennit holders, and applicants for construction permit holders review the reconinendations contained in Section V of NUREG/CR 0660 and prepare and submit a report within days of the date of this letter containing a detailed response to each reconinendation.
Each response should (a) demonstrate compliance with the recomendations, (b) present specific reasons why the recommendation is not applicable to your plant or the measures that you have in place which are equivalent to or exceed those of the recom-mendation, or (c) describe the specific measures that will be taken to implement the recommendation as well as the scheduled date of its implementation.
Further, in regard to the turbocharger gear drive changeover recommendation, unique to one engine vendor and the very limited accumulative life expectancy of the initial components, (see NUREG/CR 0660,Section V, item A-3 and Appendix F) provide the following: (a) mconstruct, to the best of your ability from the available plant information, the total accumulated time-load-speed history of the turbocharger on each diesel engine, (b) relate the total accumulated time-load-history of each emergency onsite diesel engine turbocharger to the engine vendor's calculated life expectancy for these components, and (c) indicate your schedule for implementing the turbocharger gear drive changeover recommendation in order to preclude the failure of one or more engines during a demand for onsite emergency AC power.
As in the case of the December 15, 1977, letter requesting generic information, this request was approved by GA0 under a blanket clearance number B 180225 (R0072); this clearance expires July 31, 1980.
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