ML20117C564
| ML20117C564 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Crane |
| Issue date: | 03/01/1984 |
| From: | Seyfrit K NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD) |
| To: | Starostecki R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20114F930 | List:
|
| References | |
| FOIA-84-616 NUDOCS 8505090460 | |
| Download: ML20117C564 (1) | |
Text
T UNITED STATES
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MEMORANDUM FOR:
Richard W. Starostecki, Director Division of Project and Resident Programs NRC Region I s
FROM:
Karl V. Seyfrit, Chief Reactor Operations Analysis Cranch, AE00
SUBJECT:
EXTENSION OF TMI-1 SALP REVIEW In accordance with your February 8, 1984 memorandum, AE0D has performed a supplementary LER review for TMI-1. The review covered 13 LERs which were written about events which occurred between October 1, 1983 and January 31, 1984. The caliber of the LERs which were reviewed for this supplemental period was essentially the same as that of the original period (October 1, 1982 to September 30,1983). Consequently, we have no significant additions to our original TMI-1 LER review (memorandum from K. V. Seyfrit to R. W. Starostecki, " Evaluation of LERs for Three Mile Island Nuclear Station, Unit 1, for the Period from October 1, 1982 to September 30, 1983 - AE00 Input to SALP Review," dated November 2, 1983).
Please contact Hal Ornstein at FTS 492-4439 if you have any questions regarding this matter, k/,
Karl V. Seyfri, Chief Reactor Operations Analysis Branch Office for Analysis and Evaluation of Operational Data cc:
J. Van Vliet, NRR E. L. Conner, RI 8505090460 841002
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PDR FOIA BARFIEL84-616 PDR 4>'
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,F NUCLEAR REGULATORY COMMISSION
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REGION I
'I 531 PARK AVENUE KING oF PRUSSIA. PENNSYLVANIA 19406
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FEB 2 91984 MEMORANDUM FOR:
D. G. Eisenhut, Director, Division of Licensing, NRR pd. Heltemes, Director, Office for Anaysis and Evaluation of Operational Data T. T. Martin, Director, Division.'of Engineering and Techni-cal Programs, Region I
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FROM:
R. W. Starostecki, Director, Division of Project and Resident
- Programs, Region I
SUBJECT:
EXTENSION OF TMI-1 SALP ASSESSMENT PERIOD In order to provide a more current assessment of license performance prior to an NRC Commission decision on the restart of TMI-1 (currently projected for June 1984), we are hereby extending the assessment period by four months, from Sep-tember 30, 1983 to January 31, 1984.
Consequently, the assessment will cover a sixteen (16) month period.
Please review the SALP input you previously pr$vided, update the material as ne'cessary for the four additional months and submit the update to E.L. Conner of my staff by March 16, 1984.
If no update of your previcus input in required; -
please advise Mr. Conner (FTS 488-1355) of that fact.
We expect to have a SALP Board meeting on April 2, 1984.
Your efforts and cooperation are appre n
qs m -e.4 R. W. Starostecki, Director Division of Project and Resident Programs cc:
-T. Murley, RI J. Allan, RI DPRP Branch Chiefs DETP Branch Chiefs DPRP Section Chiefs DETP Section Chiefs J. Stolz, NRR J.. Van Vliet, NRR pa sq -
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COUTH CAROLINA ELECTRIC C2 GA3 COMPANY Po;t oppec3 tee COLuustA. SQUTH CAROUNA 29218 C.W.OtxON.JR.
0 vice PassicsNT uvetaan o.eaations October 10, 1983 Mr. James P. O'Reilly Regional Administrator U.S. Nuclear Regulatory Commission Region II, Suite 2900 101 Marietta Street, N.W.
Atlanta, Georgia 30303
SUBJECT:
Virgil C. Summer Nuclear Station Docket No. 50/395 Operating License No. NPF-12 Q,_.ThirtyDayWritten, Report R 83-110
Dear Mr. O'Reilly:
Please find enclosed Licensee Event Report #83-110 for Virgil C.
Summer Nuclear Station.
This report is being submitted in accordance with Technical. Specification 3 2.5 Action Statement.
O This Action Statement was entered during a loss of Main Turbine Q
Generator load event which occurred on September 12, 1983 This report includes supplemental information as requested by the Nuclear Regulatory Commission during the meeting held on September 16, 1983, to discuss this event.
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Should there be any questions, please call us at your convenience.
Very truly yours
- 0. W.
- ixon, r.
ARK:OWD/mac Enclosure cc:
V. C. Summer C. L. Ligon (NSRC)
E. C. Roberts G. J. Braddick E. H. Crews, Jr.
D. J. Richards T. C. Nichols, Jr./O. W. Dixon, Jr.
NRC Res. Inspector H. N. Cyrus J. B. Knotts, Jr.
Group Managers I&E (Washington)
O. S. Bradham Document Management R. B. Clary Branch O. A. Price INPO Records Center t
A. R. Koon NPCF D. A. Lavigne File (Lic./Eng.)
J. F. Heilman t.~
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NUCLEAR REOU TO RY COMMISSION p
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9 *I 101 MARIETTA STREET. N.W.
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ATLANTA. GEORGI A 30303 c e'A: $C
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OCT 138 MEMORANDUM FOR: John A. Olshinski, Director, Division of Engineering and Technical Programs FROM:
R. C. Lewis, Director, Division of Project and Resident Programs
SUBJECT:
DESIGN ADEQUACY OF MAIN STEAM RELIEF VALVE TAILPIPE 10" VACUUM BREAKERS As indicated in the enclosed memorandum from the Senior Resident Inspector for Browns Ferry, the licensee has had several redesign problems with the 10" main steam relief valve tailpipe vacuum breakers.
Due to the numerous tests and redesigns, some accomplished following installation and use during plant operations, the validity of the licensee's actions are in question.
The specific items for which a regional position is requested is addressed in the enclosed memorandum.
It is requested that you evaluate the memorandum and its attached test data and provide a regional position for the noted items.
it.c, W R. C.
.ewis
Enclosure:
Memo, Floyd Cantrell from G. L. Paulk, dated September 26, 1983 cc w/o encl:
F. S. Cantrell G. L. Paulk
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OCT 131983 SSINS 9162 MEMORANDUM FOR:
Edward L. Jordan, Director, Division of Engineering and Quality Assurance, IE Richard W. Starostecki, Director, Division of Project and Resident Programs, RI Charles E. Norelius, Director, Division of Project and Resident Programs, RIII James E. Gagliardo, Director, Division of Resident, Reactor Project and Engineering Programs, RIV Thomas W. Bishop, Director, Division of Resident, Reactor Project and Engineering Inspection, RV FROM:
Richard C. Lewis, Director, Division of Project and Resident Programs
SUBJECT:
POTENTIALLY GENERIC PROBLEM AT FARLEY REGARDING THE DETACHMENT OF THE DISC FROM ITS DISC ARM ON MSIV Q2NI]V0028 The enclosed potentially generic issue data sheet concerning the disc to disc arm stud / fastener failure in the 32-inch Atwood Morrill pneumatic operated swing check valve is forwarded for information per TI 2500/3.
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h_ Richard Lewis
Enclosure:
Potentially Generic Issue Data Sheet No. RII:DPRP:83-13 cc w/ enc 1:
C. J. Heltemes, Jr., AE0D R. L. Bangart, RIV G. Holahan, ORAB, NRR CONTACT:
R. E. Carroll 242-5543 W
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ENCLOSURE Data Sheet No.:RII:DPRP-83-13 Appendix A TI 2500/3 4/1/80 POTENTIALLY GENERIC ISSUE DATA SHEET Facility Farley Docket Nc(s).
50-364 Date of Event 09/17/83 Inspection or other Report LER 83-039/0lT-0 1.
Brief Description of Issue (Not required if included in supporting data)
On 9/17/83, while Unit 2 was in Mode 3 and being cooled down for a refueling outage, Main Steam Isolation Valve Q2N11V002B, (loop 2 down stream), could not be fully closed.
When plant conditions permitted CONTINUED ON PAGE 2 2.
How Found (If appropriate) 3.
Why Consicered Potentially Generic (i.e. - reference applicable criteria or give reason)
It is believed that this type of pneumatic operated swing check valve is used specifically for MSIV(s) at Trojon, Palisades and Indian Point facilities and may be used at other nuclear power plants as well.
4.
II R. E. Carroll, 'Jr.
F. S. Cantrell/D. M. Verrelli Region Originator Section Chief / Branch Chief 5.
Other Region Reporting That The Problem Has Also Been Identified By Them Region
, Chief
, Reporting
, Docket No.
6.
Evaluation by IE:HQ Bulletin / /
Circular / /
Information Notice / /
Other No further action required
/ /
Data Sheet No.:RII:DPRP-83-13 2
- 1. Continued (9/19/83), an investigation was conducted and revealed that the inability to fully close this MSIV was caused by the failure of all four disc fasteners resulting in the valve disc becoming separated from the disc arm.
These valves are designed with Belleville washers to absorb the impact of MSIV closure under steam flow conditions'and ensure proper disc to seat align-ment. This design apparently allowed flexure during flow conditions while the valve was on the open stop.
It is believed that this flexure exposed the fastener threads, (disc end), to cyclic loads which resulted in excessive thread wear and eventual failure. The four fasteners on MSIV
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Q2N11V0028 failed and at least one fastener was found loose on each of the five remaining MSIVs (a total of eight additional fasteners were loose).
All parts were recovered.
A design change is being implemented to preclude recurrence of this problem. The design change consists of:
Adding two open stops to the body of each MSIV.
These new stops and a.
the existing stop will restrain the valve disc while in the normally open position, thus eliminating the flexure motion of the disc.
b.
Replacing the four studs used to fasten the disc to the disc arm with studs that have interference fit threads.
This design will eliminate the need for the fastener studs to rely on the Belleville washers to maintain preload. This change is to eliminate the excessive wear of the threads due to disc movement.
Utilizing an interference fit between the fastener stud hex nut and the c.
stud and installing a set screw through the pitch diameter of the stud and nut. This will assure constant preload on the disc assembly via the Bellevile washers.
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JAN 131934 Docket No. 50-348/364 MEMORANDUM FOR:
Richard C. Lewis, Director Division of Project and Resident Programs, RII FROM:
Robert L. Baer, Chief Engineering and Generic Communications Branch Division of Emergency Preparedness and Engineering Response Office of Inspection and Enforcement
SUBJECT:
POTENTIALLY GENERIC PROBLEM AT FARLEY REGARDING THE DETACHMENT OF THE DISC FROM ITS ARM ON MSIV Q2N11V002B Your memorandum of October 13, 1983, forwarded the subject potential generic problem.
Conversations with the valve manufacturer, Atwood & Morrill Company, indicate that they notified the other sites which have this valve (Farley Unit 1, Ginna, Indian Point Units 2&3, and Palisades) on September 27, 1983.
This notification, a copy of which is enclosed as Enclosure 1, recommended that the utilities inspect the valves at their facilities.
Because the manufacturer has notified the affected utilities, it is felt that issuance of a bulletin or information notice is not warranted at this time.
N x. %
Robert L. Baer, Chief Engineering and Generic Communications Branch Division of Emergency Preparedness and Engineering. Response, IE
Enclosure:
Atwood & Morrill Company letter dated September 27, 1983 cc: w/ enclosure R. W. Starostecki, RI R. L. Baer, IE gE. Carroll, RII C. E. Norelius, RIII F. S. Cantrell, RII R. J. Kiessel, IE S. A. Schwartz, IE A. W. Dromerick, IE E. L. Jordan, IE D. M. Verrelli, RII
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CONTACT:
essel, IE
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VALVE AND FLOW CONTT.0L EOU:PMENT SPECIALISTS POWER PLANT. OIL & GAS. MARINE & INDUSTRIAL SERVICE ATWOOD cMORRILLCO INC.
ossionens Ano unsuraevunans siwes isoo 28s CANAL STREET SALEM. MASSACHUSETTS 01970 PHONE 617 744 5690 TELEX 94 0299 September 27, 1983 Power Authority of the State of New York Indian Point 3 Nuclear Power Plant Bleakly Avenue
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. Buchanan, NY 10511 Attention:
Mr. A. Frobrich
Subject:
Atwood & Morrill Swing Stop Main Steam Isolation Valves Installed at Indian Point 3 Nuclear Power Plant Gentlemen:
As you are aware Atwood & Morrill has notified you in the past of in-service damage experienced by the subject valves.
This letter is intended to inform you of another occurrence at Alabama Power Farley Unit 2.
The damage experienced at the Farley Unit 2 Plant is primarily to the studs, nuts and washers which attach the disc to the disc arm.
The damage appears to be of the vibration induced variety.
We recommend that you inspect these valves at your installation.
Please advise if we can be of any assistance in this > natter.
Very truly yours, A
OD M0 R L C., INC.
ds Vice President, Engineering SNS/ dab cc:
A.H. Webber R.A. Genier L.C. Hutton V.W. Toneatti
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