ML20215N775
| ML20215N775 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 10/31/1986 |
| From: | Kane W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Corbin McNeil Public Service Enterprise Group |
| Shared Package | |
| ML20215N776 | List: |
| References | |
| NUDOCS 8611070260 | |
| Download: ML20215N775 (5) | |
See also: IR 05000354/1986050
Text
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00T 311986
Docket No. 50-354
Public Service Electric & Gas Company
ATTN: Mr. C. : A. McNeill, Jr.
Vice President - Nuclear
Post Office Box 236
Hancocks Bridge, New Jersey 08038
Gentlemen: Augmented Inspection Team Report No.-50-354/86-50
This refers to the NRC Augmented Inspection Team inspection conducted by this
office on September 25 - October 3, 1986 at the Hope Creek Generating Station,.
Hancocks Bridge, New Jersey.
This inspection was conducted by a team led by
Mr. E. C. Wenzinger and included representatives-of the Office of Nuclear Reactor
Regulation and Inspection and Enforcement.
The team performed an indepth analysis
of the anomalies that occurred in th9 loss of offsite power testing during the
unit's Startup Test Program.
The findings of this inspection were discussed with
you and members of your staff by Mr. Wenzinger at the conclusion of the inspection.
The areas examined during this special inspection are discussed in the NRC Region
I Inspection Report which is enclosed with this letter.
The areas examined were
prescribed by the team Charter and were selected to provide NRC management with
a comprehensive analysis of the root causes of the problems noted during testing.
Recent events at Hope Creek and at other. plants were also reviewed to determine
if there were weaknesses common among these issues and the loss of offsite power
test observations. The inspection was also designed to provide the basis for con-
tinuing or relaxing the actions to which you committed, as documented-in NRC Region
I Confirmatory Action Letter (CAL) 86-12, issued on September 24, 1986.
In summary, the team determined that the results of the loss of offsite power tests
-indicated certain weaknesses in the design, construction, and testing programs for
Hope Creek. With the exception of the problems found related to the Bailey solid
state logic module system, the team found the weaknesses to be minor ~in nature.
For the Bailey . system, however, the team identified concerns with the adequacy of
bench and surveillance testing and with the significant failure rate which was
higher than expected.
Accordingly, Region I management met with you and your staff on October 15, 1986
to discuss these concerns and your proposed corrective actions.
Subsequently, we
found your proposed actions were sufficient to warrant relaxation of the CAL and
continuation of the Startup Test Program.
Appendix A to this letter listed those issues for which the team considers en-
forcement action should be considered.
You will be informed of any enforcement
action which we find to be necessary through our routine inspection program.
Because of your previous submittals to us in connection with your response to the
Confirmatory Action Letter, no reply to this letter is required.
However, we re-
quest that you consider submitting a response addressing your views on the factual
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00T 311986
content and the conclusions drawn in this report.
This submittal is not subject
to the clearance procedures of the Office of Management and Budget as required by
the Paperwork Reduction Act of 1980, PL 96-511.
Your cooperation with us in this matter is appreciated.
Sincerely,
Original Signed ay;
William F. Kane, Director
Division of Reactor Projects
Enclosures:
1.
Appendix A, Potential Enforcement Issues
2.
Region I Augmented Inspection Team Report No. 50-354/86-50
cc w/encls:
P. R. H. Landrieu, Vice President - Engineering (Newark)
R. S. Salvesen, General Manager, Hope Creek Operations
A. E. Giardino, Manager, Station Quality Assurance
R. L. Mitt 1, General Manager, Nuclear Assurance and Regul_ation
W. H. Hirst, Manager, Joint Generation Projects Department, Atlantic
Electric Company
L. A. Reiter, General Manager - Licensing and Reliability
Rebecca A. Green, Bureau of Radiation Protection
Public Document Room (PDR)
Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector
State of New Jersey
S. Mayo, Tokyo Electric Power Company
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- OCT 311986
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bec w/encls:
J. Sniezek, DEDR0GR
H. Denton, NRR
R. Bernero, NRR
E. Adensam, NRR
D. Wagner, NRR
J. Taylor,.IE-
J. Partlow, IE
E. Jordan, IE
J. Rosenthal, IE.
J. Jacobson, IE Vendor Programs Branch
J. Heltemes, AE00
W. Lanning, AE00
DRP Directors, Region II-V
-Region I Docket-Room (with concurrences)
Management Assistant, DRMA (w/o enc 1)
DRP Section Chief
T. Murley, RI
W. Kane, RI
S. Ebneter, RI
T. M.irtin, RI
R. Bores, RI
T. Kashy, RI
J. Wiggins, RI
L. Stanley, IE Consultant
H. Eichenholz, RI
J. Shedlosky, RI.
P. Earen, RI
C. Sctulten, NRR
E. Wellinger, RI
R. Gallo, RI
L. Wercholm, RI
RI:DRS
RI:DRP
RI:DRS
RI:DRP
Wiggins/meo*
Wenzinger*
Ebneter*
Kane*
10/31/86
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Region I Docket-Room (with concurrences)
Management Assistant, DRMA (w/o encl)
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Robert.J. Bores, DRSS
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J. Rosenthal, IE /
W. Lanning, AE00 <
T. Koshy, DRS
J. Wiggins, DRS
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J. Shedlosky, SRI, Millstone 3
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D. Hunnicutt, RIV
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J. Taylor, IE /
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APPENDIX A
POTENTIAL ENFORCEMENT ISSUES
Based on the results of the Augmented Inspection Team inspection conducted Septem-
ber 25 to October 3, 1986, the following were identified as issues potentially
warranting enforcement' action in terms of violations or deviations.
The issues
below have been annotated to provide a reference to the applicable section of the
Augmented Inspection Team report in which they are discussed.
1.
Adequacy of the bench testing afforded to the Bailey 862 system (Section V).
2.
Compliance to NRC Regulatory Guide 1.97 for power supplies for the safety
relief valve acoustic monitoring system, source / intermediate range monitor
drives, and various level and temperature sensors (Section III.E and IV.E).
3.
Safety relief valve H was stuck open due to solenoid damage (Section IV.A).
4.
Adequacy of standby liquid control system squib valve test procedure (Section
IV.B).
5.
Star _ tup Test Program controls for deferring tests (Section IV.C).
6.
Procedure controls for safety evaluations performed by' the Operations Organi-
zation (Section IV.C).
These matters will be reviewed during future inspections, and enforcement actions
will be taken as appropriate.
.