ML20198E815
| ML20198E815 | |
| Person / Time | |
|---|---|
| Issue date: | 08/29/1985 |
| From: | Major R Advisory Committee on Reactor Safeguards |
| To: | Ebersole J Advisory Committee on Reactor Safeguards |
| Shared Package | |
| ML20151L176 | List: |
| References | |
| FOIA-86-266 ACRS-GENERAL, NUDOCS 8605280277 | |
| Download: ML20198E815 (9) | |
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o UNITED STATES o NUCLEAR REGULATORY COMMISSION j ,I ADVISORY COMMITTEE ON REACTOR SAFEGUARDS e WASHINGTON, D. C. 20656
..... August 29, 1985 MEMORANDUM FOR: Jesse Ebersole, Chairman, ACRS Subconsnittee on Reactor Operations FROM: Richard Major, Senior Staff Engineer M L / / /
SUBJECT:
TENTATIVE SCHEDULE AND STATUS REPORT FOR THE
- SEPTEMBER 10, 1985 MEETING OF ACRS SUBCOMITTEE ON REACTOR OPERATIONS, WASHINGTON, DC ,
l Enclosed is the tentative schedule for the subject meeting. NOTE THE -
SHIFT IN DAYS FROM MONDAY, SEPTEMBER 9 TO TUESDAY, SEPTEMBER 101 The purpose of the meeting is to discuss recent plant operating experience.
The Offices of Inspection and Enforcement and Nuclear Reactor Regulation have identified a number of current events for discussion with the Subcommittee. I have also collected several incidents for discussion.
Following the Subcommittee's review of these incidents a limited number of these will be picked for presentation to the full ACRS during the September, 1985 full Committee Meeting on Thursday, September 12, 1985 from 8:45 a.m. to 10:45 a.m. ,
The meeting will start at 1:00 p.m. on Tuesday, September 10, 1985 and run until approximately 5:00 p.m. The meeting will be held at
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1717 H St., N.W., Washington, D.C., Room 1046. The meeting will be entirely open to the public.
If as you review the list of events to be discussed you do not see listed an incident in which you or the other members are interested, please let me know. I'll try,to get it added to the agenda. I can be reached at (202) 634-1414.
Attendance by the following ACRS members is anticipated and hotel reservations have been made as indicated. If anyone is unable to make the meeting, please call us or the hotel and cancel your reservations so' that we are not billed.
Members Hotel Nights Mr. Ebersole Carlyle -
9/9 thru 13 Mr. Michelson Days Inn ~
9/9 thru 13 Mr. Reed Days Inn 9/9 thru 13 Dr. Remick Makes own --
D. Ward' Makes own --
C. Wylie. Days Inn 9/9 thru 13 ,
8605280277 860508 PDR FOIA MURPHY 86-266 PDR ,
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n Jesse Ebersole 2 - August 29, 1985 By copy of this memo, members of the NRC Staff and other participants who will be making presentations to the Subcommittee are reminded of the Subcommittee's need for twenty paper copies of all slides, training aids, and reports presented to the Subcommittee.
Enclosure:
As stated cc: ACRS Members
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R. Fraley, ACRS M. Libarkin, ACRS T. McCreless, ACRS J. McKinley, ACRS G. Quittschreiber, ACRS P. Boehnert, ACRS R. Minogue, RES, 1130-55 J. Taylor, IE, EWW-359 J. Davis, NMSS, 958-SS H. Denton, NRR, P-428 D. Eisenhut, NRR, P-428 R. Hernan, NRR, P-433 -
J. Partlow, IE, EWS-360 E. Jordan, IE, EWS-305 S. Schwartz, IE, EWW-359 T. Ankrum, IE, EWS-305 J. Milhoan, IE, EWS-360 E. Weiss, IE, EWS-305 G. Lanik. IE, EWS-305 E. Rossi, IE, EWS-305 J. Heltemes, AE00 T.' Murley, Region I J. Nelson Grace, Region II J. Keppler, Region III R. Martin, Rigion IV J. Martin, Region V
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5 PROPOSED SCHEDULE ACRS REACTOR OPERATIONS SUBCOMMITTEE MEETING SEPTEMBER 10, 1985
- - - - - WASHINGTON, D.C.
1:00 PM 1. Chairman's Introduction - J. Ebersole (10 min) 1:10 PM 2. Discuss Recent Plant Operating (3 hrs,35 min)
Experience (SEEATTACHEDLIST) 3:00 PM *** 8REAK ***
(10 min) 4:45 PM 3. Select items to be presented to the (15 min) full Committee on Thursday, .
September 12, 1985 from 8:45 to 10:45 A.M.
5:00 PM 4. Adjourn
Attachment:
List of Recent Significant Events G
e ENCLOSURE l l
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As of August 28, 1985
< Tentative Agenda for ACRS Subcommittee Meeting o W +e Qer 10, 1984 1:00 p.m>
Room 1046, H Street RECENT SIGNIFICANT EVENTS Presenter / Office Date Plant Event telephone 12/84 Seabrook Main Steam Safety Valve Flow Deficiency G. Hammer, NRR 492-8963 7/2/85 Fermi 2 Inadvertent Criticality D. Lynch, NRR 492-7050 7/21/85 Turkey Pt. 3 Post Trip Loss of Auxi.11ary Feedwater J. Henderson, IE 492-9654 7/23/85 Turkey Pt. 3 MSIV Problem V. Hodge, IE 492-7275 4-8/85 Turkey Pt. 3 Recent Inverter Failures H. Bailey, IE 492-9006 7/23/85 Point Beach 1 Loss of Offsite Power H. Bailey, IE 492-9006 7/23/85 Point Beach Safety Injection Recirculation Line M. Caruso, NRR Deficiency -
492-7940 8/7/85 Maine Yankee Common Mode Problem with Steam Generator J. T. Beard,.NRR Pressure Indication 492-7465 8/16/85 Dresden 2 Loss of Offsite Power R. Gilbert, NRR 492-7128 8/19/85 Browns Ferry Seismic Design of Cable Trays E. Weiss, IE 492-9005 8/20/85 Callaway 1 Electric Power Transient T. Alexion, NRR 492-8629 6-8/85 Waterford Startup Experience Comparison Wm. Jones, IE Wolf Creek 492-7613
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Callaway Catawba Byron 8/85 Peach Bottom New information on pipe cracks G. Gears, NRR ,
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SSINS No.: 6835 IN 85-XX .,,- 9 iP (0 /'u >.
UNITED STATES NUCLEAR REGULATORY COMMISSION M, f/
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v t/\ d 0FFICE OF INSPECTION AND ENFORCEMENT 5 WASHINGTON, D.C. 20555 f i g/ @/ c
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~IE INFORMATION NOTICE NO. 85-XX: MAIN STEAM SAFETY VALVE TEST FAILURES AND RING SETTING ADJUSTMENTS Addressees:
All,[ressurized, dater eactor (PWR) nuclear power reactor facilities holding an
- k operating license (0L) or a construction permit (CP).
Purpose:
This information notice is.being provided as a notification of a potentially significant problem pertaining to spring-actuated main steam safety valves (See Figure 1), that may possess less than the full rated flow capacity required for overpressure protection of the secondary cooling system in PWRs. It is expect-ed that recipients will review the information for applicability to their facilities and consider actions, if appropriate, to preclude a similar problem at their facilities. However, suggestions contained in this information notice do not constitute NRC requirements; therefore, no specific action or written response is required.
Description of Circumstances:
In the fall of 1984, Public Service of New Hampshire se:1t the main steam safety
- valves for their Seabrook plant to W@ e Laboratories for testing to determine the appropriateness of their ring settings. Specifically, the tests were to BM
' determine if the "as-shipped" ring settings of the valves would allow the required disc trael with minimum tailpipe backpressure and to determine the effects on valve disc travel for a range of backpressures between 180 and 390 psig.
The results of the tests indicated that the valves'co'uld not achieve the
. required disc travel with the factory-set ring setting (+155 notches). The disc travel achieved was 50% of the full lift required to develop full flow steam flow capacity as required by the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (code). Adequate lift was not attain-
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able even with the largest diameter tailpipe.
During the tests, the upper (guide) ring setting was adjusted from +155 to 0 and to +25 to achieve the Code required disc travel. This is a substantial adjustment.
i Subsequently, the licensee consulted with the valve manufacturer and agreed upon ring settings of +25 for the guide ring and -25 (the original setting) for the lower (nozzle) ring.
On October 14, 1982, Duke Power Company notified the NRC that they had deter-mined that pressurizer Code safety valve design flow, based upon known ring.
settings, could not be fully mainta'in~e d if called upon. This was determined from data from the generic relief and safety valve test program recently completed by the Electric Power Research Institute. This problem was limited i l
to some Dresser valves on Babcock and Wilcox designed PWRs. Consultation with icensees, B&W, and Dresser resulted in resetting of ring settings in a number
{ofplants. -
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s l Full flow, full size test of 3
th2 sort described in this notice are not normally (
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performed by either the licensee or valve vendor for large primary or secondary '
safety valves, nor are they required by the ASME Code,Section III. [The !
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valves are certified by extryolations on data from tests of smaller valves.]
i While the Seabrook valves are Crosby 6R10, manufactured by Crosby Valve and Gage Company, similar problems (my exist with any 'prfmary or secondary safety where certification is done by extrapolation.
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, 1 IN 85-XX OMD' September, 1985 Page of No specific action or written response is required by' this information notice.
'If you have any questions about this matter, please contact the Regional Administrator of the appropriate regional office or this office Edward L. Jordan, Director Division of Emergency Preparedness and Engineering Response Office of Inspection and Enforcement 4
Technical
Contact:
Mary Wegner, IE (301)492-4511
Attachment:
. List of Recently Issued IE Information Notices
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