ML20040B903
| ML20040B903 | |
| Person / Time | |
|---|---|
| Issue date: | 11/21/1980 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| Shared Package | |
| ML19297C884 | List: |
| References | |
| FOIA-81-326 NUDOCS 8201260555 | |
| Download: ML20040B903 (8) | |
Text
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- o UNITED STATES
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KING oF PRUSSIA, PENNSYLVANIA 19406 November 21, 1980 THOSE LISTED BELOW:
0 PREVENTION OF DAMAGE DUE TO WATER LEAKAGE INSIDE CONTAINMENT (OCTOBER 17, 1980 INDIAN POINT 2 EVENT)
The enclosed Inspection and Enforcement Bulletin (EncTosure 1) was forwarded to the holders of a nuclear power reactor operating license listed Enclosure 2 for action as indicated in Enclosure 3 and to the holders of a nuclear power reactor construction permit listed in Enclosure 4 for information as indicated in Enclosure 5.
Ce 8
H. Grier
/
Director
Enclosures:
1.
List of Licensees Receiving IE Bulletin No. 80-24 for Action 3.
Sample Letter (Action) 4.
List of Licensees Receiving IE Bulletin No. 80-24 for Information 5.
Sample Letter (Information)
CONTACT:
D. L. Caphton (8-488-1266)
DISTRIBUTION:
w/ ADDRESSEES LIST Division of Technical Support, MPS (ATTN:
R. A. Hartfield) p.If Mail & Files Central Files H. W.. Woods, IE V
8201260555 811002 PDR FOIA JEWETT81-326 PDR
SSINS No.:
6820 Accession No.:
8008220270 TEB 80-24 UNITED STATES OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 November 21, 1980 IE Bulletin No. 80-24:
PREVENTION OF DAMAGE DUE TO WATER LEAKAGE INSIDE CONTAINMENT (OCTOBER 17, 1980 INDIAN POINT 2 EVENT)
Description of Circumstances:
On October 24, 1980 IE Information Notice No. 80-37 described an event that occurred at the Indian Point Unit 2 (IP-2) facility:
On October 17, 1980, upon containment entry for repair to a nuclear instrument, it was discovered that several inches of water had accumulated on the containment floor without the operators' knowledge.
This accumulation was later determined to have amounted to over 100,000 gallons which flooded the reactor vessel pit and wetted the lower nine feet of the reactor vessel while the reactor was at operating temperature.
The flooded condition resulted from the following ccmbination of condihions:
(1) There were significant multiple service water leaks from piping and fan coolers onto the containment floor.
This syster. had a history of leakage; (2) Both containment sump pumps were inoperable, one due to blown fuses and the other due to binding of its float switch; (3) The significance of two containment sump level indicating lights which indicated that the water level was continuously above the pump-down level was not recognized by the operators; (4) There was no high water level alarm and the range of sump level indicating lights failed to indicate the overflowing sump level; (5) The moisture level indicators for the containment atmosphere did not indicate high moisture levels, apparently due t.c an error in calibration and/or ranging which made them insensitive to the moisture levels resulting from relatively small cold water leaks; (6) The hold-up tanks which ultimately receive water pumped from the containment sump also received water from other sources (Unit 1 process water, lab drain water, etc).
These other water sources masked the effect of cessation of water flows from the Unit 2 sump; (7) The fan cooler condensate wier level measuring instruments were not properly calibrated; (8) There was no water level instrumentation in the reactor vessel pit and the pumps were ineffective since they discharge to the containment floor for ultimate removal by the containment sump pumps.
This Bulletin is issued to enable the NRC staff to formulate requirements for long term generic corrective actions which will be the subject (s) of future NRC actions.
The bulletin requires short term actions which will preclude IP-2 type events at other plants in the interim before the longer term generic actions are accomplished.
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IEB 80-24 November 21 1980 0
Page 2 of 3 Acticns to be Taken by Licensees:
1.
Provide a summary description of all open* cooling water systems present inside containment.
Your description of the cooling water systems must include:
(a) Mode of operation during routine reactor operation and in response to a LOCA; (b) Source of water and typical chemical content of water; (c) Materials used in piping and coolers; (d) Experience with system leakage; (e) History and type of repairs to coolers and piping systems (i.e., replacement, weld, braze, etc.); (f) Provisions for isolating portions of the system inside containment in the event of leakage including vulner-ability of those isolation provisions to single, failure; (g) Provisions for testing isolation valves in accordance with Appendix J to 10 CFR 50 (h) Instrumentation (pressure, dew point, flow, radiation detection, etc.)
and procedures in place to detect leakage; and (i) Provisions to detect radioactive contamination in service water discharge from containment.
2.
For plants with open cooling water systems inside containment take the following actions:
Verify existence or provide redundant means of detecting and promptly a.
alerting control room operators of a significant accumulation of water in containment (including the reactor vessel pit if present).
b.
Verify existence or provida positive means for control room operators to determine flow from containment sump (s) used to collect and remove water from containment.
Verify or establish at least monthly surveillance procedures, with c.
appropriate operating limitations, to assure plant operators have at least two methods of determining water level in each location where water may accumulate.
The surveillance procedures shall assure that at least one method to remove water from each such location is available during power operation.
In the event either the detection or removal l
systems become inoperable it is recommended that continued power i
operation be limited to seven days and added surveillance measures be instituted.
- d. Review leakage detection systems and procedures and provide or verify ability to promptly detect water leakage in containment, and to isolate the leaking components or system.
Periodic containment entry to inspect i
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- An Open system utilizes an. indefinite volume, such as a river, so that leakage l
from the system could not be detected by inventory decrease.
In addition, a direct radioactive pathway might exist to outside containment in the event of a LOCA simultaneous with a system leak inside containment.
A closed system l
utilizes a fixed, monitored volume such that leakage from the system could l
be detected ffom inventory decrease and a second boundary exists to prevent loss of containment integrity as a result of a system leak inside containment.
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IEB 80-24 Novemb:r. 21, 1980
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Pags 3 of 3 for leakage should be considered.
the Beginning within 10 days of the date of this bulletin, whenever in (a) through reactor is operating and until the measures describ The e.
tainment atmosphere measures shall include where practical (considering co i n or remote '
visual surveillance to check for water leakage. impractic i
for n subsequent water leakage at the first plant shutdown for any reaso to receipt of this bulletin, Establish procedures to notify the NRC of any service water system (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> leaks within containment via a special licensee event report f.
f a containment with written report in 14 days) as a degradation o boundary.
' ament provide For plants with closed cooling water systems inside co into containment.
3.
the provi-Provide a written report, signed under oath or affirmation, under nse to the sions of Section 182a of the Atomic Energy Act of 1954, in respo i
Include in your
- 4.
abcve items within 45 days of the date of this bullet n tions in response to items 2 (a) through (d).
Washington, D.C.
dd Director of the appropriate Regional Office with 'a copy forwar e t
to the Director, NRC, Office of Inspection and Enforcemen,
20555.
t t the If you desire additional information regarding this matter please con appropriate IE Regional Office.
30, 1980.
Approval 8180225 (R0072); clearance expires Novemberidentified generic problems, Approved by GAO,wIs given under a blanket clearance specifically for
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Enclosura 2 IE Bulletin No. 80-24 November 21, 1980 RECENTLY ISSUED IE BULLETINS Date Issued Issued To Bulletin Subject No.
11/14/80 All holders 'of a Failures of Solenoid power reactor OL 80-23 Valves Manufactured by or CP Valcor Engineering Corporation Automation Industries, 9/12/80 All holders of a radiography license 80-22 Model 200-520-008 Sealed-Source Connectors 11/6/80 All holders of a Valve Yokes Supplied by power reactor 80-21 Malcolm Foundry Company, Inc.
OL or'CP 8/29/80 All holders Revision 1 Boron Loss from of a BWR power to 79-26 BWR Control Blades reactor OL 8/15/80 All holders of a Revision 1 Failures of Mercury-power reactor Wetted Matrix Relays in OL or CP to 80-19 Reactor Protective Systems of Operating Nuclear Power Plants Designed by Comburtion Engineering 7/31/80 All holders of a Failures of Westinghouse power reactor OL 80-20 Type W-2 Spring Return to or CP Neutral Control Switches 7/31/80 All holders of a 80-19
_ Failures of Mercury-power reactor OL Wetted Matrix Relays in or CP Reactor Protective Systems of Operating Nuclear Power Plants Designed by Combustion Engineering Maintenance of Adequate 7/24/80 All holders of a PWR power reactor 80-18 Minimum Flow Thru OL or CP Centrifugal Charging Pumps Following Secondary Side High Energy Line Rupture 8/22/80 All holders of a Supplement 3 Failure of Control Rods BWR power reactor to 80-17 to Insert During a OL or CP Scram at a BWR O
ENCLOSURE 2 LIST OF HOLDERS OF NUCLEAR POWER REACTOR OPERATING LICENSES RECEIVING IE BULLETIN NO. 80-24 (FOR ACTION)
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 Company M/C Nuclear Docket No. 50-293 ATTN:
Mr.
A. V. Morisi 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 Consolidated Edison Company of Docket Nos. 50-03 New York, Inc.
50-247 ATTN:
Mr. Peter Zarakas Vice President 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 Sixth Ave'nue Pittsburgh, Pennsylvania 15219 Jersey Central Power and Light Company Docket No. 50-219 ATTN:
Mr. Ivan R. Finfrock, Jr.
Vice President Madison Avenue at Punch Bowl Road Morristown, New Jersey 07960 a
2 Docket No. 50-309 Maine Yankee Atomic Power Company ATTN:
Mr. Robert H. Grace Senior Engineer-Licensing 25 Research Drive 01581 Westborougn, Massachusetts Docket Nos. 50-289 Metropolitan Edison Company 50-320 ATTN:
Mr. R. C. Arnold Senior Vice President 100 Interpace Parkway 07054 Parsippany, New Jersey Docket No. 50-220 Niagara Mohawk Power Corporation ATTN:
Mr. T. E. Lempges Vice President Neclear Generation 300 Erie Boulevard West 13202 Syracuse, New York Docket Nos. SD-336 Northeast Nuclear Energy Company 50-245 ATTN:
Mr. W. G. Counsil Vice President - Nuclear Engineering and Operations P. O. Box 270 Hartford, Connecticut 06101 Docket Nos. 50-277 Philadelphia Electric Company 50-278 ATTN:
Mr. S. L. Dal troff Vice President Electric Production 2301 Market Street Philadelphia, Pennsylvania 19101 Docket No. 50-286 Power Authority of the State of New York Indian Point 3 Nuclear Power Plant ATTN:
Mr. S. S. Zulla Resident Manager P. O. Box 215 Buchanan, New York 10511 Docket No. 50-333 Power Authority of the State of New York James A. FitzPatrick Nuclear Power Plant ATTN:
Mr. R. J. Pasternak Resident Manager P. O. Box 41 Lycoming, New York 13093
3 Puolic Service Electric and Gas Company Docket Nos. 50-272 ATTN:
Mr. F. W. Schneider 50-311 Vice President - Production 80 Park Plaza Newark, New Jersey 07101 Rochester Gas and Electric Corporation 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 Pcwer Corporation Docket No. 50-271 ATTN:
Mr. Robert L. Smith Licensing Engineer 25 Research Drive Westborough, Massachusetts 01581 Yankee Atomic Electric Company Occket No. 50-29 ATTN:
Mr. James A. Kay Senior Engineer-Licensing 25 Research Drive Westborough, Massachusetts 01581 A
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ENCLOSURE 3 SAMPLE LETTER (ACTION)
Docket No(s).
Date NAME AND ADDRESS Gentlemen:
j The enclosed IE Bulletin No. 80-24, "Preventien of Damage Due to Water Leakage Inside Containment (October 17, 1980 Indian Point 2 Event)" it, forwarded to you for action.
A written response is required.
In order to assist the NRC in evaluating the value/ impact of each Stlletin on licensees, it would be helpful if you would provide 'an estimate of the manpower expended in conduct of the review and preparation of the report (s) required by the Bulletin.
Please estimate separately the manpower associated with corrective-actions following identification of problems through the Bulletin.
If you desire additional information regarding this matter, please contact this office.
Sincerely, t
Boyce H. Grier Director
Enclosures:
1.
List of Recently Issued IE Bulletins CONTACT:
D..L.
Caphton (215-337-5266)
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o ENCLOSURE 4 LIST OF HOLDERS OF A NUCLEAR POWER REACTOR CONSTRUCTION PERMIT RECEIVING IE BULLETIN NO. 80-24 (FOR INFORMATION)
Northeast Nuclear Energy Company Docket No. 50-423 ATTN:
Mr. W. G. Counsil Vice President - Nuclear Etigineering and Operations P. O. Box 270 Hartford, Connecticut 06101 Duquesne Light Company Docket No. 50-412 ATTN:
Mr. E. J. Woolever Vice President 435 Sixth Avenue Pittsburgh, Pennsylvania 15219 Jersey Central Pcwer & Light Company Docket No.-50-363 ATTN:
Mr. I. R. Finfrock, Jr.
Vice Presider.t 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 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. G. K. Rhode Vice President System Project Management c/o Miss Catherine R. Seibert 300 Erie Boulevard, West Syracuse, NY 13202
2 Pennsylvania Power & Light Company Docket Nos. 50-387 ATTN:
Mr. Norman W. Curtis 50-388 Vice President Engineering and Construction - Nuclear 2 North Ninth Street Allentcwn, Pennsylvania 18101 Philadelphia Electric Company Docket Nos. 50-352 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
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Newark, New Jersey 07101 Public Service Coinpany 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 Rochester Gas & Electric Corporation Docket No. 50-485 ATTN:
Mr. J. E. Arthur Chief Engineer 89 East Avenue Rochester, New York 14649 e
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ENCLOSURE 5 SAMPLE LETTER (INFORMATION)
Docket Nc(s).
Date NAME AND ADDRESS Gentlemen:
The enclosed IE Bulletin No. 80-24, " Prevention of Damage Due to Water Leakage Inside Containment (October 17, 1980 Indian Point 2 Event) is forwarded to you for information.
No written response is required.
If you desire additional information regarding this matter, please contact this office.
Sincerely, Boyce H. Grier Director
Enclosures:
1.
List of Recently Issued IE Bulletins CONTACT:
D. L. Caphton (215-337-5266) 9 e
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