ML19330B910
| ML19330B910 | |
| Person / Time | |
|---|---|
| Site: | Hatch, Millstone  |
| Issue date: | 07/22/1980 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | John Miller GEORGIA POWER CO. |
| References | |
| NUDOCS 8008070195 | |
| Download: ML19330B910 (2) | |
Text
' je =rog#o UNITED STATES NUCLEAR REGULATORY COMMISSION e.
/
g REGION 11 5
,, a 101 MARIETT A ST., N.W.. SUITE 3100 Q
'g ATLANTA. GEORGIA 30303 j'
e ooe,*
JUL 2 21980 h ply Refer To:
RH:
0 0-321 (0-366 Georgia Power Company ATTN:
J. H. Miller, Jr.
Executive Vice President 270 Peachtree Street Atlanta, GA 30303 G ntlemen:
A Enclosed is Supplement No. 2 to IE Bulletin No. 80-17 which requires action by you with regard to your power reactor facility (ies) with an operating license.
This transmittal confirms the information and action required that was conveyed by telephone to you on July 19, 1980.
i In order to assist the NRC in evaluating the value/ impact of each Bulletin on it would be helpful if you would provide an estimate of the manpower licensees, of the review and preparation of the report (s) required by expended in conduct Please estimate separately the manpower associated with corrective the Bulletin.
actions necessary following identification of problems through the Bulletin.
Should you have any questions regarding this Bulletin or the actions required by r] you, please contact this of fice.
V Sincerely,
.s James P. O'Reill Director
Enclosures:
1.
Supplement No. 2 to IE Bulletin No. 80-17 2.
List of Recently Issued IE Bulletins cc w/ encl:
M. Manry, Plant Manager C. E. Belflower, Site QA Supervisor W. A. Widner, Vice President and General Manager-Nuclear Generation I i
\\s' 800soro y
r 9
SSINS No.:
6820 Accession No.:
Il UNITED STATES 8006190032 V
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C. 20555 July 22, 1980 IE Bulletin No. 80-17 Supplement No. 2 FAILURE 1 Rii,3 WD BY TESTING SUBSEQUENT TO FAILURE OF CONTROL RODS TO INSERT DURING C$cp>3 AT A BWR Description Cf Circumstances:
At abost kn a.m. on July 19, 1980, a manual scram test was initiated at Dresden hg A 3.
This test was initiated in accordance with the require-ments si NOnlletin No. 80-17.
The scram itself was accomplished (i.e.,
control ug inserted). Following the scram, the Scram Discharge Volume (SDV) was m%iM by UT in accordance with Item #3 of IE Bulletin No. 80-17.
The UT cheQbed the normal draining of the SDV at a time when personnel conduc4 @ test believed the SDV to be empty.
However, the UT check reveal %gistram discharge west header bank to be 80% filled with water (i.e..We* nly the drain was not successful).
P " N stion, it appeared that the' SDV vent system did not function due U
g;)
to a 4%I. check valve (i.e., a ball check valve functioning as a vacuum break & & ball' check valve is installed in a tee connection downstream of theit sive in a one-inch vent header which tcrminates in the reactor build%Mpeent drain tank (RBEDT). The ball check valve provides a vent path tgastor building atmosphere in the event the vent header does not.
The ve*% itself provides a path to other interconnections and extends into th% 2nder the surface of water normally contained there.
Additiate4annation has also resulted from scram testing at other BWRs as follou h old, the Scram Discharge Instrument Volume (SDIV) drain valve 1-
"Nhnstalled so that pressure in the SDIV tended to unseat the disk. This resulted in leakage out of the SDIV during the N s was corrected by reversing and reinstalling the valve.
The
- % were performed on July 12 and 13 and the drain valve was N before return to power operations on July 17, 1980.
2.
Istone Unit I, the. scram te'sts were performed successfully on ough 14.
The function of the 10-second delay on scram reset f2.(j) of IE Bulletin No. 80-17) was tested separately from the Review of the separate test results by plant personnel
,that the scram reset delay feature was not functioning in the h ts due to a wiring error on the circuit boards.
This was A
O x a du oe e
r IE Bulletin No. 80-17 July 22, 1980
[.sT Supplement No. 2 Page 2 of 2 v
3.
At Browns Ferry Unit No. 1, a ' test scram involving two rods was performed on July 19, 1980.
Tae test showed normal response of level switches in the SDIV. When proceeding to drain the SDIV, however, the SDV did not empty as required and expected. A vacuum in the SDV apparently existed which kept the system from draining.
Subsequently, the vacuum was cleared by operator actions and the volume drained properly. Tests are continuing toward determination of the cause and to measure the vacuum.
4.
At Nine Mile Point Unit No. 1, one rod failed to scram during the manual scram test on July 14, 1980. This was due to a failure of the scram pilot valve for that rod.
In view of the above-described events, the following actions in addition to those specified in IE Bulletin No. 80-17, including Supplement No. 1, are to be taken by BWR licensees.
1.
Each BWE licensee with a SDV vent system that depends on any component other than the vent valve alone for proper venting must provide an alter-nate vest path centinuously open to building atmosphere on the side of the vert valve piping away from the SDV. This alternate vent path must be positite in its function at all times (i.e., a vent must be effective regardino of component operability other than the vent valve).
O)
Plants Emme made corrections by providing a vent through a standpipe open
(_
to bui3J64 atmosphere. This was done at Browns Ferry Unit No. 3 and is being Dur; at Dresden Units 2 and 3.
It is noted that due consideration to radh6cgical aspects should be included.
An aliesste vent path must be provided within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> following the telephoe notification on July 19, 1980 in order to continue or commence operatssw 2.
Reportsx writing within 5 days of the date of this Bulletin Supplement the ceW2metion of your action in response to the above. Reports shall be subakad to the Director of' the appropriate NRC Regional Office and a copy 5dkEl be forwarded to the NRC Office of Inspection and Enforcement, Divithraf Reactor Operations Inspection, Washington, D.C. 20555.
More informeka on the details of the Dresden and Browns Ferry events and modificationtin be obtained by contacting the Dresden and/or Browns Ferry operating supetsion. In addition, we understand that a General Electric Company Lashn6ce is available for consultation at (408)925-3188.
For all TodIHetweter power reactor facilities with a construction permit, this Bulletsrmio for information only and no written response is required.
Approved _by GM, B180225 (R0072); clearance expires 7-31-80.
Approval was given under.udlanket clearance specifically for identified generic problems.
O
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1 s
T
-e IE Bulletin No. 80-17.(Supplement No. 2)
Enclosure
/N July 22, 1980 k.)
RECENTLY ISSUED IE BULLETINS Bulletin Subject Date Issued Issued To No.
Supplement 1 Failure of Control Rods 7/18/80 All BWR power reactor to 80-17 to Insert During a Scram facilities holding OLs at a BWR 80-17 Failure of Control Rods 7/3/80 All BWR power reactor to Insert During a Scram facilities holding OLs at a BWR 80-16 Potential Misapplication of 6/27/80 All Power Reactor Rosemount Inc., Models 1151 Facilities with an and 1152 Pressure Transmitters OL or a CP with Either "A".or "D" Output Codes 80-15 Possible Loss Of Hotline 6/18/80 All nuclear facilities With Loss Of Off-Site Power holding OLs 80-14 Degradation of Scram 6/12/80 All BWR's with an
/~h Discharge Volume Capability OL V
80-13 Cracking In Core Spray 5/12/80 All BWR's with an "Spargers OL 80-12 Decay Heat Removal System 5/9/80 Each PWR with an OL Operability 80-11 Masonry Wall Design 5/8/80 All power reactor facilities with an OL, except Trojan 80-10 Contamination of 5/6/80 All power reactor Nonradioactive System and facilities with an Resulting Potential for OL or CP Unmonitored, Uncontrolled Release to Environment 80-09 Hydramotor Actuator 4/17/80 All power reactor Deficiencies operating facilities and holders of power reactor construction permits 80-08 Examination of Containment 4j7/80 All power reactors with Liner Penetration Welds a CP and/or OL no later
(~'g than April 7, 1980 V
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