ML20202D237
| ML20202D237 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 02/06/1998 |
| From: | Hehl C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Olivier L BOSTON EDISON CO. |
| Shared Package | |
| ML20202D240 | List: |
| References | |
| 50-293-97-13, EA-97-615, EA-98-052, EA-98-52, NUDOCS 9802170023 | |
| Download: ML20202D237 (4) | |
See also: IR 05000293/1997013
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February 6,1998
EA 97 615
EA 98 052
Mr. Leon J. Olivier
Vice President - Nuclear Operations / Station Manager
Boston Edison Company
Pilgrim Nuclear Power Station
600 Rocky Hill Road
Plymouth, Massachusetts 02360 5599
SUBJECT:
PILGRIM INSPECTION REPORT 50 293/97-13 AND NOTICE OF
VIOLATION
Dear Mr. Olivier:
On January 6,1998, the NRb completed an inspection at the Pilgrim Nucleer Power
Station in Plymouth, Massachusetts. The enclosed report presents the results of that
inspection.
During the seven weeks covered by this inspection period, the conduct of activities at the
Pilgrim facility was characterized by safe operations. However, two violations of NRC
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requirements were identified that are cited in the enclosed Notice of Violation. The first
violation involved ineffective corrective actions to ameliorate erratically operating reactor
vessel flange temperature elemente. Your staff identified that the temperature indication of
the differential, between the reactor vessel flang. ind adjacent shell, exceeded the
technical specification limit of 145 degrees. Although later your staff determined that the
145 degree limit was not actually violated, our review of the maintenance history for the
temperature elements ident;fied three opportunities in 1997 to resolve loose or detached
temporary temperature elaments. The erratic operation of these temperature elements
challenged the operating crew during power ascension. The second violation involved a
self-disclosing event where an electrical relay of the wrong voltage rating was installed into
an anti::ipated transient without scram (ATWS) system cabinet that subsequently
overheated. For this latter violation, we chose not to exercise discretion due to the
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multiple errors involved, and also in part due to a similar NRC observation involving '&C
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technicians staging a wrong part for use in the field during anc+'er work activity this same
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inspection period. We remain concerned that your staff did not detect and correct these
problems at an earlier stage.
included in this report is the closeout of the criticality monitor issue involving the potential
violation of 10 CFR 70.24, Criticality Accident Requirements. We havo determined that
- your facility was in violation of this regulation in that you did not have in place either a
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criticality monitoring system for storage and handling of new (non-irradiated) fuel or an
NRC approved exemption to the regulation.
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9802170023 900206
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L. Olivier
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Thus, as described in the inspection report, your facility was in violation of 10 CFR 70.24.
Numerous other f acilities have similar circumstances. The NRC has reconsidered this
violation and concluded based on the information discussed in the report that, although a
violation did exist, it is appropriate to exercise enforcement discretion for Violations
involving Special Circumstances in accordance with Section Vil B.6 of the " General
Statement of Policy and Procedures for NRC Enforcement Actions" (Enforcement Policy),
NUREG 1600. The bases for exercising this discretion are the lack of safety significance of
the failure to meet 10 CFR 70.24;the failure of the NRC staff to recognize the need for an
exemption during the licensing process; the prior NRC position concerning the lack of a
need for an exemption; and finally, the NRC's intention to amend 10 CFR 70.24 through
rulemaking to provide for administrative controls in lieu of criticality monitors.
Therefore, I have been authorized after consultation with the Director, Office of
Enforcement, to exercise enforcement discretion and not issue a violation for this matter.
Pending the amendment to 10 CFR 70.24, further enforcement actior' will not be taken for
failure to meet 10 CFR 70.24 provided you obtain an exemption to this regulation before
the next receipt of fresh fuel or before the next planned movement of fresh fuel.
We also reviewed and closed your program implemented under Generic LetM (GL) 8910,
" Safety-Related Motor-Operated Valve Testing and Surveillance." Closure is based on:
your demonstration of the design-basis capability of each GL 8910 program motor-
operated valves, and your commitment, documented in a letter dated December 11,1997,
to obtain as part of your long-term program additionalindustry information or analyses to
validate certain valve factor assumotions. Also, there are nine MOVs with relatively small
design margins which should be addressed for long term consideration.
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Also, during our review of LER 97-15, an apparent violation was identified and is being
considered for escalated enforcement action in accordance with the " General Statement of
Policy and Procedure for NRC Enforcement Actions" (Enforcement Policy) NUREG-1600.
This violation involves the reliability of the salt service water (SSW) pump operation.
Specifically, with a single SSW pump operating and supplying one coolant loop, under
degraded voltage. the SSW breaker overload heater protection relay for the pump could trip
rendering the pu..ip inoperable. We recognize the positive nature of the self identification
and resolution of this issue. Because this is an apparent violation, no Notice of Violation is
presently being issued for tnis inspection finding. You will be advised by separate
correspondence of the results of our deliberations on this matter. No response regarding
this apparent violation is require at this time.
You are required to respond to this letter and should fo!Iow the instructions specified in the
enclosed Notice when preparing your respinse. In your response, you should document
the specific actions taken and any additiorul actions you plan to prevent recurrence. Your
response may reference or include previous docketed correspondence if the
correspondence adequately adresses the required response. After reviewing your
response to this Notice, including your proposed corrective actions and the results of
future inspections, the NRC will determine whether further NRC enforcement action is
necessary to ensure compliance with NRC regulatory requirements.
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L. Olivier.
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in accordance Nith 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter
and its enclosures will be placed in the NRC Public Document Room (PDR). To the extent
possible, your response should not include and personal privacy, proprietary, or safeguards
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information so that it can be placed in the PDR without redaction.
The responses directed by this letter and the enclosed Notice are not subject to the .
clearance procedures of the Office of Management and Budget as required by the
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Paperwork Reduction Act of 1980, Pub. L. No. 96.511,
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Your cooperation with us is appreciated.
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Sincerely,
Original Signed By:
Cherles W. Hehl, Director
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Division of Reactor Projects
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Docket No.: 50 293
License No.: DPR 35
Enclosures:
2. Inspection Report 50-293/97-13
3. BECo Handout at Enforcement Conference on November 21,1997
cc w/ encl:
C. Goddard, Plant Manager
N. Desmond, Regulatory Relations
D. Tarantino, Nuclear Information Manager
R. Hallisey, Department of Public Health, Commonwealth of Massachusetts-
The Honorable Therese Murray
B. Abbanat, E,epartment of Public Utilities
Chairman, Plymouth Board of Selectmen
Chairman, Duxbury Board of Selectmen
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Chairman, Nuclear Matters. Committee
Plymouth Civil Defense Director
Paul W. Gromer, Massachusetts Secretary of Energy Resources
James Shaer, Legislative Assistant
J. Fleming
A. Nogee, MASSPIRG
Regional Administrator, FEMA
Office of the Commissioner, Massachusetts Department of Environmental Quality
Engineering
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Office of the Attorney General, Commonwealth of Mass:chusetts
T. Rapone, Massachusetts Executive Office of Public Safety
Chairman, Citizens Urging Responsible Energy
Commonwealth of Massachusetts, SLO Designee
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L. Olivier
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Region I Docket Room (with concurrences)
PUBLIC
Nuclear Safety Information Center (NSIC)
NRC Resident inspector
H. Miller, RA/W. Axelson, DRA
C. Cowgill, CRP
R. Summers, DRP
C. O'Daniell, DRP
J. Wiggins, DRP
- L. Nicholson, DRS
C. Miskey, DRS
R. Zimmerman, NRR
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J. Goldberg, OGC
J. Lieberman (OEMAIL), OE
D. Holody, EO, RI
Distribution w/enci (VIA E-MAIL):
B. McCabe, OEDO
R. Eaton, NRR
A. Wang, NRR
R. Correia, NRR
F. Talbot, NRR
DOCDESK
Inspection Program Branch, NRR (IPAS)
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DOCUMENT NAME:G:\\ BRANCH 5\\PIL9713.lNS
To ,ocehre e copy of this document.
ete in the boa: *C' = Copy without attachment / enclosure
'E' = Copy with attachment / enclosure -
'N' = No copy
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OFFICE
Rl/DRP (f ,f
Rl/DRP //"
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NAME
RLaura V '/
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CCowgill
DATE
01/29/98 (
01/3/98
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OFFICIAL RECORD COPY
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