IR 05000293/1985019
| ML20138C956 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 10/11/1985 |
| From: | Harpster T, Lazarus W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20138C944 | List: |
| References | |
| 50-293-85-19, NUDOCS 8510230113 | |
| Download: ML20138C956 (5) | |
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'k U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-293/85-19 Docket No.
50-293
License No.
DpR-35 Priority Category C
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Licensee:
Boston Edison M/C Nuclear 800 Boylston Street Boston, Massachusetts 02199 Facility Name:
Pilgrim Generating Station
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Inspection At:
Plymouth, Massachusetts Inspection Conducted:
September 4-6, 1985 Inspectors:
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W. fa;4rus[Jenior Emergency Preparedness date Specialist T. Harpster,- Chief, Emergency Preparedness Section L. Tripp, Chief, Reactor Projects Section 3A M. McBride, Resident Inspector, Pilgrim
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G. Wiliman, Battelle, PNL L. Smith, Battelle, PNL
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J. Lynch, Battelle, L
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Approved by:
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T. HarpstTer', C ef, Emergency Preparedness pte/
Section
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Inspection Summary:
Inspe on on September 4-6, 1985 (Report No. 50-293/85-19)
Areas Inspected:
Routine announced emergency preparedness inspection to observe the licensee's~ annual full participation emergency exercise performed on September 5, 1985. The inspection involved 147 inspector hours by a team of 7 NRC and NRC contractor personnel.
Results: No violations were identified. The licensee's emergency response
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actions for this exercise scenario were adequate to provide protective measures for the health and safety of the public. Two significant concerns were identi-
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fied:
1) Radiation exposure to're entry teams was not adequately evaluated, and 2) No plans or procedures are in effect.to-implement a relocation to the i
Alternate EOF.
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1.
Persons Contacted
- C. Mathis, Nuclear Operations Manager P. Mastrangelo, Chief Operating Engineer
- A. Oxsen, Vice President, Nuclear Operations J. Seery, Technical Section Head
- T. Sowdon, Radiological Section Head P. Smith, Chief Technical Engineer-
- Denotes those present at the exit meeting.
2.
Emergency Exercise The Pilgrim Generating Station full participation exercise was conducted on September 5, 1985.
A.
Pre-Exercise Activities Prior to the emergency exercise, NRC Region I representatives had telephone discussions and met with licensee representatives to review the scope and content of the exercise scenario. As a result of these discussions, revisions were made to the scenario and supporting data sheets.
The NRC observers and licensee observers and controllers attended a scenario briefing on September 4, 1985.
The emergency response actions expected during the various phases of the scenario were discussed.
The scenario included the following events:
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High Pressure Coolant Injection (HPCI) pump steam line break with worker contaminated and injured.
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Loss of Reactor Building Closed Cooling Water System (RBCCWS)
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Reactor feedwater fails to trip, causing loss of vessel level control
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Relief valves manually operated to control reactor pressure
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Release of radioactivity from HPCI steam line break
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Reactor Building evacuation Fuel shipping cask falls, damaging the spent fuel pool with a
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resultant uncovering of spent fuel I
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Partial melting of spent fuel with resultant release of
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radioactivity The above events caused activation of the licensee's emergency facilities and also permitted state and local governments to exercise their Emergency Plans.
B.
Activities Observed D'uring the conduct of the licensee's exercise, NRC team members made
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detailed observations of the activation :nd :t;-antation of the emergency organization; activation of emergency response facilities; and actions of emergency response personnel during the operation of the emergency response facilities.
The following activities were observed:
Detection, classification, and assessment of the scenario
events; i
l2 Direction and coordination of the emergency response;
Notification of licensee personnel and offsite agencies of
pertiner.t information;
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Assessment and projection of radiological (dose) data and
consideration of protective actions; Provisions for in plant radiation protection;
Performance of offsite, onsite, and in plant radiological
surveys; Maintenance of site security and access control;
Performance of technical support;
-Performance of repair and corrective actions;
j Communications /information flow, and record keeping; and
Management of Recovery Operations.
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The NRC team noted that the licensee's activation and augmentation i
of the emergency organization; activation of the emergency response facilities; and actions and use of the facilities were generally
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consistent with their emergency response plan and implementing l
procedures. The team also noted the following actions of the licensee emergency response organization that were indicative of
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their ability to cope with abnormal plant conditions:
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Emergency response personnel appeared generally knowledgeable
in performing their duties and maintained an active role in i
demonstrating assigned functions in accordance with emergency procedures.
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Control room personnel demonstrated teamwork and effectively
used the established Emergency Action Levels for classification
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of the events.
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The Emergency Director made prompt conservative decisions when
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declaring Site Area and General Emergencies. State personnel
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in EOF were well briefed on the status of the simulated emergency and projections for potential worst case protective action recommendations to expect.
Good correlation was noted between dose assessment calculations
with information collected by field sample teams.
The following areas were identified which degraded overall response
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and require evaluation and corrective action by the licensee:
Inadequateconsiderationwasgiveni$oradiationexposures
received by personnel on re-entry teams.
Personnel were allowed to re-enter the spent fuel pool area with general levels of 800 R/hr. One individual on the team approached the edge of the spent fuel pool where direct radiation from the uncovered fuel would be estimated at greater than 100,000 R/hr.
There are no procedures in place which define how such situa-tions would be evaluated and controlled to maintain radiation exposures at a reasonable level.
In the cases observed, severe overexposures would likely have resulted, with very limited gain in mitigation of the accident. The licensee agreed to review this area, establish appropriate controls, and train personnel involved to 'mprove performance in this area. When controls are in effect and personnel trained, the licensee has committed to inform NRC Region I and perform a drill.which demonstrates performance in this area.
This item is unresolved (50-293/85-19-01).
The present EOF is unshielded with n'o ventilation protection.
- Similar scenarios could be expected to necessitate relocation to the Alternate EOF several miles away. There are presently no procedures in effect describing how/when relocation would be accomplished. The licensee is drafting appropriate procedures to cover relocation. This item is unresolved and will be reviewed ia a subsequent inspection (50-293/85-19-02).
During the site evacuation, accountability wasn't completed
until 48 minutes after the evacuation was announced. NUREG-0654 guideline for this fur >ction is 30 minutes. Contributing factors were 1) difficulty in paintaining accountability in the TSC and OSC areas. and 2) performance of a manual check of ID card racks instead of performing a check with the security computer.
The licensee is evaluating various means to improve accountability of onsite personnel (50-293/85-19-03).
Communications between the Control Room, TSC, and EOF used
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regular telephone speaker phones, which in several instances resulted in unintelligible or lost information and in general degraded the flow of information (50-293/85-19-04).
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The Emergency Director did not provide guidance to the TSC
Coordinator.
Coordination with the Control Room and Recovery Center and the TSC was much better (50-293/85-19-05).
Too much raw data concerning the situation was provided to state
personnel in the EOF. Much was too technical and should have been discussed and reduced to essential information before passing on to the state (50-293/85-19-06).
Important information was not displayed or treno d in the EOF
for the use of decision makers.
Time had to be used searching phone logs for information regarding times of important events (50-293/85-19-07).
There is no access control established for the E0F. The
Emergency Director could be distracted from his principal duties by being forced to interface with many different levels of state response teams (50-293/85-19-08).
3.
Exit Meeting The inspectors attended the licensee's critique on September 6,1985.
following the critique, the NRC team leader summarized the observations made during the exercise as detailed in this report (See detail 1 for attendees).
At no time during the inspection was any written material provided to the licensee by the inspectors.