ML20009E220
| ML20009E220 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley, Millstone, Calvert Cliffs, Peach Bottom, Salem, Nine Mile Point, Indian Point, Oyster Creek, Hope Creek, Pilgrim, Susquehanna, Seabrook, Limerick, Vermont Yankee, Haddam Neck, Ginna, Sterling, Yankee Rowe, Maine Yankee, FitzPatrick, 05000363, 05000516, 05000517, Shoreham, Crane  |
| Issue date: | 03/25/1981 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 8107270243 | |
| Download: ML20009E220 (4) | |
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LIST OF HOLDERS OF NUCLEAR POWER REACTOR OPERATING LICFNSES AtJi CONSTRUCTICN PERMITS RECEIVING IE INFORMATION NOTICE NO. 81-10 Baltimore Gas and Electric Company Docket Nos. 50-317 ATTN:
Mr. A. E. Lundvall, Jr.
50-318 Vice President, Supply P. O. Box 1475 Baltimore, Maryland 21203 Boston Edison Cempany M/C Nuclear Docket No. 50-293 ATTN: Mr. A. V. Morisi i
Nuclear Operations Support Manager 800 Boylston Street Boston, Massachusetts 02199 Connecticut Yankee Atomic Power Company Docket No. 50-213 ATTN: Mr. W. G. Counsil Vice President - Nuclear Engineering and Operations P. O. Box 270 Hartford, Connecticut 06101 l
Consolidated Edison Company of Docket Nos. 50-03 New York, Inc.
50-247 ATTN: Mr. John D. O'Toole Assistant Vice President - Nuclear Affairs and Quality Assurance 4 Irving Place New York, New York 10003 Duquesne Light Company Docket No. 50-334 ATTN:
Mr. C. N. Dunn Vice President Operations Division 435 Sixtn Avenue Pittsburgh, Pennsylvania 15219 Jersey ~ Central Power and Light Company Docket No. 50-219 ATTN: Mr. Ivan R. Finfrock, Jr.
l Vict. President Oyster Creek Nuclear Generating Station P. O. Box 388 Forked River, New Jersey 08731 p
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2 Maine Yankee Atomic Power Company Docket No. 50-309 ATTN: Mr. Robert H. Groce
' Senior Engineer-Licensing 1671 Worcester Road
-Framingham, Massachusetts 01701 Metropolitan Edison Company Docket No. 50-289 ATTN: Mr. H. O. Hukill Vice President and Director of TMI-l P. 0. Box 480 Middletown, Pennsylvania 17057 Metropolitan Edisor6 Company Docket No. 50-320 ATTN: Mr. G. K. Hovey
.Vice President and Director of TMI-2 1
P. O. Box 480 Middletown, Pennsylvania 17057 Niagara Mohawk Power Corporation Docket No. 50-220 ATTN: Mr. T. E. Lempges Vice President i
Nuclear Generation 300 Erie Boulevard West 4
Syracuse, New York 13202 Northeast nut. ar Energy Company Docket Nos. 50-336 ATTN: Mr. W. G. Counsil 50-245 Senior Vice President - Nuclear 50-423 Engineering and Operations P. O. Box 270 Hartford, Connecticut 06101 Philadelphia Electric Company Docket Nos. 50-277 ATTN:
Mr. S. L. Daltroff 50-278 Vice President Electric Production 2301 Market Street Philadelphia, Pennsylvania 19101 Power Authority of the State of New York Docket No. 50-286 Indian Point 3 Nuclear Power Plant ATTN: Mr. S. S. Zulla Resident Manager P. O. Box 215 Buchanan, New York 10511 i
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3 Power Authority of the State of New York Docket No. 50-333 James A. FitzPatrick Nuclear Power Plant ATTN: Mr. R. J. Pasternak Resident Manager P. O. Box 41 Lycoming, New York 13093 ATTN: Mr. F. W. Schneider-Docket Nos. 50-272 Public Service Electric end Gas Company 50-311 Vice President - Production 80 Park Plaza - 15A Newark, New Jersey 07101 Rochester Gas and Electric Corporatien Docket No. 50-244 ATTN: Mr. John E. Maier Vice President Electric and Steam Production 89 East Avenue Rochester, New York 14649 Vermont Yankee Nuclear Power Corporation Docket No. 50-271 ATTN: Mr. Robert L. Smith Licensing Engineer
-1671 Worcester Road Framingham, Massachusetts 01701 Yankee Atomic Electric Company Docket No. 50-29 ATTN: Mr. James A. Kay Senior Engineer-Licensing 1671 Worcester Road Framingham, Massachusetts 01701 Duquesce Light Company Docket No. 50-412 ATTN: Mr. E. J. Woolever Vice President 435 Sixth Avenue Pittsburgh, Pennsylvania 15219 Jersey-Central Power & Light Company Docket No. 50-363 ATTN: Mr. I. R. Finfrock, Jr.
Vice President 260 Cherry Hill Road Parsippany, New Jersey 07054 Long Island Lighting Company,
Docket No. 50-322 ATTN: Mr. M. S. Pollock Vice President - Nuclear 175 East Old Country Road Hicksville, New York 11801
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Long Island Lighting Company Docket Nos. 50-516 ATTN: Mr. Charles P. Davis 50-517 Senior Vice President 250 Old Country Road Mineola, New York 11501 Niagara Mohawk Power Corporation Docket No. 50-410 ATTN: Mr. Gerald K. Rhode Vice President System Project Management-c/o Miss Catherine R. Seibert 300 Erie Boulevard, West Syracuse, NY 13202 Pennsylvania Power & Light Company Docket Nos. 50-387 ATTN: Mr. Norman V. Curtis 50-388 Vice President Engineering and Construction - Nuclear 2 North Ninth Street Allentown, Pennsylvania,, 18101 Philadelphia Electric Company Docket Nos. 50-352-1 ATTN: Mr. John S. Kemper 50-353 Vice President Engineering and Research 2301 Market Street Philadelphia, Pennsylvania 19101 Public Service Electric & Gas Company Docket Nos. 50-354 ATTN: Mr. T. J. Martin 50-355 Vice President Engineering and Construction 80 Park Plaza - 17C Newark, New Jersey 07101 Public Service Company of New Hampshire Docket Nos. 50-443 ATTN: Mr. W. C. Tallman 50-444' Chairman and Chief Executive Officer 1000 Elm Street Manchester, New Hampshire 03105 Rochestre Gas & Electric Corporation Docket No. 50-485 ATIN:
J. E. Arthur chief Engineer 89 Ee t Avenue
. Rochester, New York 14649 a
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.SSINS N3.:
6835 Accession No.:
8011040273 IN 81-10 UNITED STATES NUCLEAR REGULATORY CCMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WA'SHINGTON, D.C.
20555 March 25, 1981 IE Information Notice No. 81-10:
INADVERTENT CCNTAINMF.NT SPRAY OUE TO PERSONNEL ERROR Description of Circumstances:
On February 11, 1981 while in mode 5 (cold shutdown), an euxiliary unit
. operator at Sequoyah Unit 1 misunderstood a verbal instruction and opened a single valve in the residual heat removal (RHR) system.
The opened valve created a direct flow path through the RHR system from the primary calant system to the RHR containment spray header. A rapid primary system depres-surization to atmospheric pressure resulted, and a total of about 110,000 gallons of water was sprayed into the containment from the primary system and from the refueling water storage tank (RWST).
Licensees and applicants shou'd be aware of the following aspects of this event and should take appropriate steps to prevent a recurrence at their
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plant.
The auxiliary unit operator did not have.-dequate training or orientation at the particular duty station involved. A single valve at that station is part of the primary coolant system pressure boundary when using the residual heat removal (RHR) system for shutdown cooling. Thus, personnel / administrative problems and a plant design feature combined to cause the event.
Design of the control ream annunciators contributed to prolonging the event.
The panel indicating emergency core cooling system (ECCS) valve positions is designed to warn when the ECCS is not properly aligned for the injection (safety) mode. When the first valve misalignment occurs, one light comes on in an otherwise dark field of indicators, and an alarm sounds and flashes.
However, in the shutdown cooling mode, severai valves are not in their injection mode position.
Therefore, in the event at Sequoyah, the alarm light had already been on continuously for some time, the annunciator was not supposed to operate, ano one more light coming "en" in a valve position-indicating field with several lights already "on" was easily missed.
The operators thus. failed to detect the presence of the inadvertently opened valve for at least 35 minutes.
Lack of an ECCS initiation procedure for use in the shutdown cooling mode did not significantly delay recovery from this event, but potentially could have done so had the primary system been at a higher pressure. To provide injection flow for pressurizer level recovery, the operators opened the RHR system suction valve from the RWST, but they neglected tu close the RHR system suction valves from the reactor coolant system (RCS). A proper procedure would require those latter valves to be closed to prevent reactor pressure from seating a
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IN 81-10 March 25,'1981 Page 2 of 2 check valve in the RWST suction line, which would prevent the injection mode for the low pressure (RHR) pumps from being effective and delay recovery from the event.
i A similar problem with the borated water storage tar.k (BWST) check valve occurred at Crystal River 3 on July 16, 1980 while the unit was in Mode 5 with the decay heat system in use for shutdown cooling.
Impropar valve alignment on the decay heat system heat exchangers caused a rapid cooldown of the RCS which resulted in a loss of pressurizer level. When recovery was attempted by realigning the decay heat system suction to the BWST, injection flow could not be established until RCS pressure approached atmospheric conditions since the RCS suction valves remained open.
This problem would be particularly significant under a LOCA condition with the RCS temperature above boiling (Mode 4).
The information herein is being provided as an early notification of a pos-sibly significant matter that is still under review by the NRC staff. Recip-ients should review the information for possible applicability to their facilities. If NRC evaluatien so indicates, further licensee actions may be requested.
No written response to this information notice is required.
If you need additional information regarding this matter, contact the Director of the appropriate NRC Regional Office.
Attachment:
Recently issued IE Information Notices.
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.s IN 81-10 March 25, 1981 RECENTLY ISSUED IE INFORMATION NOTICES Information Subject Date Issued to Notite No.
Issued 81-08 Repetitive Failure
- 3/20/81 All holders of a of Limitorque SMB-4 power reactor Motor-To-Shaft OL or CP 81-07 Potential Problems 3/16/81 All holders of a with Water-Soluble power reactor OL Purge Dam Materials or CP Used Ouring Inert Gas Welding 81-06 Failure of ITE Model 3/11/81 All holders of a 600 Circuit Breaker power reactor 81-05 Degraded DC System 3/13/81 All holders of at Palisades a power reactor OL or CP 81-04 Cracking in Main 2/27/81 All holders of a Steam Lines power reactor OL or CP 81-03 Checklist for 2/2/81 All holders of a Licensees Making power reactor Notifications of OL Significant Events in Accordance with 10 CFR 50.72 81-02 Transportation of 1/23/81 All holders of a Radiography Devices radiography license 81-01 Possible Failures of 1/16/81 All holders cf a General Electric power reactor OL Type HFA Relays cr CP 80-45 Potential Failure of 12/17/80 All holders of a
.BWR Backup Manual power reactor Scram Capability OL or CP 80-44 Actuation of ECCS in 12/14/80 All holders of a the Recirculation Mode PWR power reactor OL While in Hot Shutdown or CP
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