ML20236G240
| ML20236G240 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 07/29/1987 |
| From: | Gucwa L GEORGIA POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| SL-2935, NUDOCS 8708040174 | |
| Download: ML20236G240 (4) | |
Text
Georgia Power Comprny 333 Piedmorst Ave.lue Acanta, Georgia 30308 Telephone 404 526 6526 Maikng Adtets' Post Office Box 4545 Atlanta, Georgia 3J302 b
Georgia Power L T. Gucwa F *' "U "" N#C '"'**
Manager Nuclear Safety and Ucensrng SL-2935 0435m X7GJ17-V120 July 29, 1987 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.
20555 PLANT V0GTLE - UNIT 1 NRC DOCKET 50-424 OPERATING LICENSE NPF-68 RESPONSE TO NRC INSPECTION REPORT Gentlemen:
Pursuant to the provisions of 10 CFR 2.201, Georgia Power Company (GPC) submits the following information in response to NRC Inspection Report 50-424/87-34 concerning the inspection conducted by Mr.
P.
G.
Stoddart of NRC Region II on May 18-22, 1987.
One apparent violation was cited.
A copy of this response has been provided to NRC Region II for review.
He believe that the Notice of Violation for NRC Inspection Report 50-424/87-34 as submitted by NRC Region II letter dated June 29, 1987, incorrectly refers to Plant Vogtle Unit 2 by docket number and as a result implies that it is in violation also.
The Report Details section of the Inspection Report specifically identifies the violation as being applicable to Plant Vogtle Unit 1
by the violation designator "50-424/87-34-01." Accordingly, our response addresses only Plant Vogtle Unit 1.
In the enclosure, transcription of the NRC violation precedes GPC's response.
870B040174 870729 PDR ADOCK 05000424 G
PDR b
I gg
. Georgia PowerA i
i U. S. Nuclear Regulatory Commission-July 29, 1987 l.
Page Two'
' Should you 'have any questions in this regard, please-contact this office ~ at any time.
Sincerely, M
L. T. Gucwa JAE/lm
Enclosure:
1.
Violation 87-34-01 and GPC Response c: Georgig Power Comoany
-Mr. R. E. Conway Mr. J. P. O'Reilly Mr. G. Bockhold, Jr.
Mr. J. F. D'Amico Mr. C. H. Hayes G0-NORMS.
Southern Comoany Services Mr. R. A. Thomas Mr. J. A. Bailey Shaw. Pittman. Potts & Trowbridae
'l Mr. B. H. Churchill, Attorney-at-Law Troutman.-Sanders. Lockerman & Ashmore Mr. A. H.-Domby, Attorney-at-Law U. S. Nuclear Regulatory Commission Dr. J. N. Grace,. Regional Administrator l
Ms. M. A. Miller,. Licensing Project Manager, NRR (2 copies) l
'Mr. J. F. Rogge, Senior Resident Inspector-0perations, Vogtle i
Georaians Aaainst Nuclear Enerav Mr. D. Feig Ms. C. Stangler 0435m
?V0776
Georgia Power 1 ENCLOSURE PLANT V0GTLE - UNIT 1 NRC DOCKET 50-424 OPERATING LICENSE NPF-68 HRC NOTICE OF VIOLATION 87-34-01 AND GPC RESPONSE y_IOLATION 50-424/87-34-01:
" Technical Specification 6.7.1 requires the establishment, implementation and maintenance of written procedures for the control of releases of radioactive materials to the environment.
Nuclear Operations Procedure 13201-01 " Gaseous Releases," in Step 4.1.4, requires the closure and tagging, with independent verification, of certain valves, including Valve No. 1-1902-U4-073.
Contrary to the above, at 6:00 a.m.
(sic) on May 18, 1987, Valve No.
1-1902-U4-073 was found in a partially opened position during a
controlled release of gases from Haste Gas Decay Tank 4, resulting in the inadvertent release to the environment of radioactive gases from Waste Gas Decay Tank 2.
This is a Severity Level IV violation (Supplement IV)."
RESPONSE TO VIOLATION 50-424/87-34-01:
Mmission or denial of alleaed violation:
Georgia Power Company (GPC) admits that the event did occur as stated in the Inspection Report.
However, after careful review of the event and 10 CFR 2, Appendix C, Supplement IV, GPC believes that the severity level should be reclassified to e severity level V, " violations that have minor safety or environmental significance."
The inadvertent release was monitored through monitor RE-014, which did not alarm during the release.
In addition, a sample (sample #2602-87) was obtained by the plant's chemistry department which substantiated that the release did not exceed Technical Specification allowable limits.
It should also be noted that on page 4 of the Inspection Report it was stated that "No Technical Specification release rate limits or offsite dose commitments were exceeded as a result of the inadvertent release."
Further, calculations have been performed which demonstrate that the projected radiation levels at the site boundary were well below the criteria specified in 10CFR2 Appendix C, Supplement IV, Paragraph D.2 for Severity Level IV violations.
Based on the foregoing information, GPC requests a downgrade in severity level to Severity Level V.
0435m E-1 07/29/87 SL-2935
k Georgia Power h ENCLOSURE (Continued)
HRC NOTICE OF VIOLATION 87-34-01 AND GPC RESPONSE ESAson for violation 1 The release of Haste Gas Decay Tank #2 through valve 1-1902-U4-073 when a release of Haste Gas Decay Tank #4 was in progress was due to a partially open valve.
Documentation is available that indicates valve 1-1902-04-073 was closed and verified closed for the release on May 17, 1987.
However, this type valve, i.e., a diaphragm valve connected to a reach rod through a clutch, may appear to be closed when in fact it is partially open.
Specifically, if the clutch on the reach rod operator is not engaged when the valve handwheel is taken closed, the handwheel will respond as if the valve is closed, when in fact, the valve will not be closed.
The plant equipment operator (PEO) who positioned valve 1-1902-U4-073 was not aware of the valve / reach rod characteristic described above.
Corrective steos which have been taken and the results achieved:
The subject valve was fully closed upon discovery of the partially open condition.
In addition, Shift Qualifiers (i.e.,
expert personnel hired to train PE0s on the proper operation of plant equipment) briefed the operating crews on the proper method to :4en and close valves having reach rods.
The PE0 Basic Training Course now includes training on valves that are positioned using reach rods.
Corrective stgos which will be takertto orevent recurrence:
Corrective actions which have already been taken and the administrative controls which already exist should prevent recurrence of this violation.
Date when full com_pliance will be achieved 1 Full compliance was achieved with the proper closure of valve 1-1902-U4-073 on May 18, 1987.
0435m E-2 07/29/87 SL-2935
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