ML19345C347
| ML19345C347 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 11/21/1980 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Mcdonald R ALABAMA POWER CO. |
| References | |
| NUDOCS 8012040472 | |
| Download: ML19345C347 (1) | |
Text
- t
- o
,.g
'o, UNITED STATES 7 %
NUCLEAR REGULATORY COMMISSION
)
E REGION 11 9
[3 0,
[
101 MARIETTA ST N.W., SUITE 3100 O
o ATLANTA, G EORGIA 30303 7
r NOV 211980
?,2 w
In Reply Refer To:
.T\\
[2
[i, RII:JP0 i %'
Wii
50-348 1~;M" 2
GI 0-364 5$
EE' m._ -
s a
C
_o r
Alabama Power Company ATTN:
R. P. Mcdonald Vice President-Nuclear Generation P. O. Box 2641 Birmingham, AL 35291 Gentlemen:
Euclosed is IE Bulletin No. 80-24 which requires action by you with regard to your nuclear power facility.
In order to assist the NRC in evaluating the value/ impact of each Bulletin on licensees, it would be helpful if you would provide us an estimate of the manpower expended in conduct of the review and preparation of the report (s) required by
<he Bulletin.
Please estimate separately the manpower associated with corrective actions necessary following identification of problems through the Bulletin.
Should you have any questions regarding this Bulletin or the actions required by you, please contact this office.
Sincerely, z' m2 9,..
f_
James P. O'Reilly" Director
Enclosures:
1.
List of Recently Issued IE Bulletins cc w/encls:
W. O. Whitt, Executive Vice President F. L. Clayton, Jr., Senior Vice President H. O. Thrash, Manager-Nuclear Generation O. D. Kingsley, Jr., Manager, Nuclear Engineering and Technical Services J. U. McGowan, Manager-Operations Quality Assurance W. G. Hairston, III, Plant Manager 6U120dU
.,r.
D
~3 uw ab
$6 SSINS No.:
6820 Accession No.:
8008220270 s
' UNITED STATES OFFICE OF INSPECTION AND ENFORCEMEhT
. WASHINGTON, D.C.
20555 November 21, 1980 IE Bulletin No. 80-24:
PREVENTION OF DAMAGE DUE TO WATER LEAKAGE (OCTOBER 17, 1980 INDIAN POIhT 2 EVEhT)
Description of Circumstances:
On October 24, 1980 occurred at the Indian Point Unit 2 (IP-2) facility.IE Information Notice N 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 fl the operators' knowledge.
gallons which flooded the reactor vessel pit and w tt dThis out to over 100,000 lower nine feet of the reactor vessel while the reactor was at operating e e the temperature.
The flooded condition resulted from the following combination of conditions:
coolers onto the containment floor.(1) There were significant multiple ser an (2) Both containment sump pumps were inoperable, one due to blown fuses sump level indicating lights which indicated that the water and the ent continuously above the pump-down' level was not recognized by the operator (4) There was no high water, level alarm and the range of sump level i di lights. failed to indicate the overflowing r,tump level; (5) The moisture level n cating indicators for the containment atmosphere did not indicate high moist insensitive to the moisture levels resulting from relatively sm leaks; (6)'The hold-up. tanks'which ultimately receive water pumped from the water containment sump.also received water from other sources (Unit I process water lab drain water, etc).
of water flows from the Unit 2 sump; (7) The fan cooler condensa measuring instruments were not properly calibrated; (8) There was no water since they discharge to the containment floor for ultima t
containment sump pumps.
This Bulletin is issued to' enable the NRC staff to formulate requirements f long term generic corrective actions which will be the subject (s) of future or NRC actions.
type events at other plants in the interim before the longer term are accomplished.
actions
1 I
l l
L IEB 80-24 November 21, 1980 Page 2 of 3 Actions 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) Frovisions for testing isolation valves in accordance with Appendix J to 10 CFR 50 (b) 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 provide positive means for control room operators to determine flow from containment sump (s) used to collect and remove water from containment.
I 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 systems become inoperable it is recommended that continued power 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
- An Open system utilizes an indefinite volume, such as a river, so that leakage from the' system could not be detected by inventory decrease.
In addition, a direct radioalctive pathway might exist to outside containment in the event of a LOCA simultaneous with a system leak inside containment.
A closed system utilizes a fixed, monitored volume such that leakage from the system could be detected from inventory decrease and a second boundary exists to prevent loss of containment integrity as a result of a system leak inside containment.
)
IEB 80-24 November 21, 1980 Page 3 of 3 for leakage should be considered.
Beginning within 10 days of the date of this bulletin, whenever the e.
reactor is operating and until the measures described in (a) through (d) above are implemented, conduct interim surveillance measures. The measures shall include where practical (considering containment atmosphere and ALARA considerations) a periodic containment inspection or remote visual surveillance to check for water leakage.
If containment entry is impractical during operation, perform a containment inspection for water leakage at the first plant shutdown for any reason subsequent to receipt of this bulletin.
f.
Establish procedures to notify the NRC of any service water system leaks within containment via a special licensee event report (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with written report in 14 days) as a degradation of a containment boundary.
3.
For plants with closed cooling water sy:tems inside containment provide a summary of experiences with cooling water system leakage into containment.
4.
Provide a written report, signad under oath or affirmation, under the provi-sions of Section 182a of the Atomic Energy Act of 1954, in response to the above items within 45 days of the date of this bulletin.
Include in your report where applicable, your schedule for completing the actions in response to items 2 (a) through (d). Your response should be sent to the Director of the appropriate Regional Office with a copy forwarded to the Director, NRC, Office of Inspection and Enforcement, Washington, D.C.
20555.
If you desire additional information regarding this matter please contact the appropriate IE Regional Office.
Approved by GAO, B180225 (R0072); clearance expires November 30, 1980. Approval was given under a blanket clearance specifically for identified generic problems.
's e se e-,=en-ey e==gr ee ep*
N*
9*** *
- 1 IEB 80-24 November 21, 1980 RECENTLY ISSUED 5 i
s.
IE BULLETINS Bulletin No.
Subject Date Issued Issued To 80-24 Prevention of Damage Due to 11/21/80 All nuclear power Water Leakage Inside Con-facilities with an tainment (October 17, 1980 OL or CP Indian Point 2 Event) 80-23 Failures of Solenoid Valves 11/14/80 All nuclear power Mauufactured by Valcor facilities with an Engineering Corporation OL or CP 80-22 Automation Industries, 9/11/80 All radiography Model 200-520-008 Sealed-licensees Gource Connectors 80-21 Valve yokes supplied by 11/6/80 All light water Malcolm Foundry Company, Inc.
reactor facilities holding OLs or cps Supplement 3 Environmental Qualification 10/24/80 All power reactor to 79-10B of Class IE Equipment facilities with an OL Supplement 2 Environmental Qualification 9/30/80 All power reactor to 79-01B of Class IE Equipment facilities with an OL 80-22 Automation Industries, 9/11/80 All radiography Model 200-520-008 Sealed-Jicensees source Connectors 79-26 Boron Loss from BWR 8/29/80 All BWR power Revision 1 Control Blades facilities with an OL 80-20 Failures of Westinghouse 7/31/80 To each nuclear Type W-2 Spring Return power facility in to Neutral Control Switches your region having an OL or a CP 80-19 Failures of Mercury-7/31/80 All nuclear power Wetted Matrix Relays in facilities having Reactor Protective Systems either an OL or a CP of Operating Nuclear Power Plants Designed by Combus-tion Engineering 80-18
- Maintenance of Adequate 7/24/80 All PWR power reactor Minimum Flow Thru Centrifucsl facilities holding OLs Charging Pumps Following and to those PWRs Secondary Side High Energy nearing licensing Line Rupture mpp 6 69M9N
'*C
-