ML20246A756
| ML20246A756 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 06/26/1989 |
| From: | Russell W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Bird R BOSTON EDISON CO. |
| References | |
| CAL-86-10, NUDOCS 8907070078 | |
| Download: ML20246A756 (24) | |
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4 Docket No. 50-293 Boston Edison Company ATTN: Mr. Ralph G. Bird Senior Vice President - Nuclear Pilgrim Nuclear' Power Station
.RFD #1 Rocky Hill Road Plymouth, Massachusetts 02360 Gentlemen:
SUBJECT:
REACTOR OPERATION UP TO FIFTY (50) PERCENT POWER
References:
(1) Boston Edison Power Ascension Test Program, dated August 31, 1988; updated October 27, 1988 (2) Confirmatory Action Letter 86-10, April 12,1986 and Supplements dated August 27, 1986 and December 30, 1988 This letter approves reactor operation up to fifty (50) percent of full power in accordance with Boston Edison Company's (BECo) Power Ascension Test Program and NRC Confirmatory Action Letter 86-10 and its' supplements. This letter neither imposes any new requirements nor releases Boston Edison from any exist-ing requirements contained in the Facility License or Technical Specifications.
The staff finds that management performance, plant material condition and operational performance support proceeding to the next phase of the Power Ascension Program.
The bases for approving the continuation of the Power Ascension Program consist of:
(1) successful completion of the Power Ascension Program up to 25% power.
(2) a comprehensive assessment of plant and personnel performance by BECo during this phase of plant startup, (3) particularly comprehensive evaluations and corrective actions by BECo for significant events that occui ed during this period, including the April 12, 1989, Reactor Core Isolation Cooling (RCIC) event and the May 3,1989, reactor scram, and (4) NRC staff inspection and l
review activities which have confirmed the safety of operations by both the l
staff and. management of BECo during this phase of plant startup.
Enclosure (1) is a summary of NRC findings which either have been or will be docketed in NRC inspection reports 50-293/89-01 and 89-05, 89-06, 89-80, 89-07, and Meeting Report 89-43. The most recent inspection activities, by the NRC Restart Staff, monitored and verified selecte'd aspects of your startup and power ascension activities including your own management assessments of the performance of your i
facility and personnel. Based upon our conclusion that the facility is being l
safely operated and satisfactorily managed, and is ready for the next phase of
(
power ascension, the NRC has no objection to plant operation at power levels up to 50% of full power.
OFFICIAL RECORD COPY WIGGINS 523 6/23/89 B - 0001.0.0 l
06/23/89 is 8907070078 890626 ADOCK 0500 3
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'l Additionally, the current status of emergency preparedness for the communities surrounding the Pilgrim Station as compiled by the staff and reported to the Commission is shown in Enclosure 2.
We continue to encourage cooperative and j
expeditious action by Boston Edison and the Commonwealth and local governments to further improve the state of emergency preparedness for'the area surrounding, t
the Pilgrim facility.
No reply to this letter is required.
Should you have questions, please contact f
the NRC Region I office promptly.
Sincerely, f
Original Signed By WILLI 1E T. RUSSELL William T. Russell Regional Administrator
Enclosures:
As stated cc w/encls:
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l L. Gustin, Vice President - Corporate Relations K. Highfill, Station Director
.R. Anderson, Plant Manager J. Keyes, Licensing Division Manager E. Robinson, Nuclear Information Manager R. Swanson, Nuclear Engineering Department Manager The Honorable Edward M. Kennedy The Honorable Edward J. Markey The Honorable Edward P. Kirby
- The Honorable Peter V. Forman Chairman, Board of Selectmen, Plymouth Chairman, Board of Selectmen, Duxbury Chairman, Board of Selectmen, Carver Chairman, Board of Selectmen, Kingston Chairman, Board of Selectmen, Bridgewater Chairman, Board of Selectmen, Marshfield Mayor, City of Taunton Plymouth Civil Defense Director P. Agnes, Assistant Secretary of Public Safety, commonwealth of Massachusetts M. Ernst, Committee on Energy, Commonwealth cf Massachusetts B. McIntyre, Chairman, Department of Public Utilities S. Pollard, Massachusetts Secretary of Energy Resources N. Johnson, Chairman, Duxbury Nuclear Committee R. Shimshak, MASSPIRG R. Boulcy, Director, Massa Jusetts Civi, Defense Agency and Office of Emergency Preparedness
.M. Conyngham, Legislative Assistant M. Jeka, Legislative Assistant i
K. Anderson, Legislative Assistant Public Document Room (PDR)
Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector Commonwealth of Massachusetts (2) 0FFICIAL RECORD COPY WIGGINS 523 6/23/89 B - 0001.1.0 06/23/89
= _ - - _ _ _ _. _
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bec w/encis:
Region I Docket Room (with concurrences)
V..Stello, ED0 J. Taylor, EDO B. Clayton, EDO T. Murley, NRR F. Mirag'11a, NRR J. Partlow, NRR S. Varga, NRR B. Boger, NRR R. Wessman, NRR D. Mcdonald, NRR j
L. Chandler, OGC l
W. Russell, RI i
J. Gutierrez, RI
_j M. Mille", RI W. Kane, RI T. Martin, RI M. Knapp, RI S. Collins, RI J. Strosnider, RI R. Gallo, RI R. Bellamy, RI J. Durr, RI J. Wiggins, RI R. Blough., RI J. Lyash, RI M. Kohl, RI R. Bores, RI C. Warren, SRI - Pilgrim T. r(im, RI - Pilgrim C. Carpenter, RI - Pilgrim DRP:RI RP:RI I
DRP:RI 1
R. BLough J. Wiggins Collins B. Russell 6/23/89 6/23/89 6/23/89 6/23/89 6\\24M 4lal'1
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ENCLOSURE 1 Assessment of Licensee Readiness for Release From NRC Approval Point
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Number 3 Permitting Operation to 50% Power I.
Background
NRC Confirmatory Action Letter No. 86-10 of April 12, 1986, and the August 27, 1986 supplemental letter identified specific technical issues to be resolved prior to facility restart.
In addition, due to other long-term management, hardware and program issues, Boston Edison Company (BECo) submitted a formal Power' Ascension Program to the NRC.
As specified in the licensee's NRC-accepted Power Ascension Test Program, the licensee must obtain the NRC Region I Regional Administrator's ag+eement to proceed beyond the 25% NRC approval point to the 50% power plateau. The program includes 'NRC Regional Administrator approval points at 5%, 25%, 50%, 75%
of full power, as well as requiring a licensee formal assessment and NRC review after completion of the Power Ascension Program, including testing at full power.
By letter dated March 3,1989, Mr. James M. Allan, acting for the Regional Admini s trator for Region I, agreed with BEco's conclusion to proceed beyond the second approval point and conduct power operations up to 25% of full power.
This enclosure provides the NRC Restart Assessment Panel's assessment of licensee performance since the licensee's release from the second approval point.
II. Chronology of Significant Plant Events March 3, 1989 Licensee received NRC agreement to proceed from second NRC approval point.
March 4, 1989 A main turbine bypass system anomaly occurred at 5:49 p.m. causing the bypass valves to close then fully open, producing a reactor pressure drop which resulted in an automatic MSIV closure and reactor scram.
All safety systems responded as designed.
Licensee performed a plant cooldown l
and placed the reactor in cold shutdown.
March 9, 1989 A licensee-requested Management Meeting was held at NRC Region I to discuss the licensee's review and evaluation of the March 4,1989 event.
March 11, 1989 Pilgrim plant was restarted and the reactor made critical at 11:05 p.m.
1 i-_____.___________._________________._
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1 March 15, 1989 Licensee successfully completed mode switch func-j tional testing, closing a technical concern asso-ciated~ with Con fi rmatory Action Letter 86-10.
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April'3, 1989 Completion of _ the test program at 5-25% power
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- plateau as described in the August 31, 1988,
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Pilgrim Nuclear Power Station Power Ascension Program.
Licensee conducted the initial presen-tation of results to the NRC Pilgrim Restart Assessment Panel.
April 12, 1989 Reactor Core Isolation Csling (RCIC) overpress-urization event during cot: duct of RCIC logic sys-i tem functional test. This resulted in lifting of 1
the suction piping relief valve and water accumu-
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lation on room floor.
An Augmented Inspection Team (AIT) was dispatched to Pilgrim on April 13, 1989, in response to event.
April 14, 1989 The NRC Restart Assessment Panel adopted an o
Apri) 12, 1989 NRC line management recommendation that the Panel review in detail the April 12, 1989 RCIC system event prior to proceeding with approval point release deliberations.
April 16, 1989 Plant' shutdown by the licensee to continue inves-tigation and repair of the possibly inoperable check' valve' in RCIC system.
Unusual Event declared from 1:35 p.m.
to 8:50 p.m.
due to initiation of shutdown.
April 19, 1989 AIT exit interview was held at NRC Region I.
April 21, 1989 BECo issued a letter to NRC Region I regarding corrective actions from the April 12, 1989, RCIC system event.
i April 28, 1989 Pilgrim plant critical at 7:45 p.m.
May 3, 1989 Turbine trip / reactor scram on high reactor vessel l
water level due to unexpected opening of "8"
Feedwater Regulating Valve (FRV).
All safety l
systems responded as designed with the exception a
of five containment isolation valves, including
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the "A" inboard Main Steam Isolation Valve (MSIV) which closed unexpectedly.
The closures of the
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containment isolation valves were attributed to a voltage transient in the power supply to the valves during a fast transfer of power sources l
upon the turbine generator trip.
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JEnclosure1 3-May 25, 1989 Pilgrim plant critical at 5:25 a.m.
f, May 26, 1989 Plant-reached 25% power.
June 8, 1989 BECo made presentation to NRC Pilgrim Restart Assessment Panel requesting approval to proceed from PATP Approval Point No. 3.
June 9, 1989 BECo identified that one channel of RCIC steam line area temperature monitoring had been rendered inoperable as a result of a lifted lead not being restored after a surveillance test con-ducted on May 14, 1989.
BECo ' immediately began an investigation.
June 13 and 14, BECo conducted a briefing for the NRC staff and
, 1989 the Pilgrim Restart Assessment Panel members on the results of its review of the RCIC steam line area temperature monitoring investigation.
III. Staff Evaluation 1.
The NRC Restart Assessment Panel considered the following approval point release criteria to evaluate the conduct of the Pilgrim Power Ascension Test Program and consider approval of the licensee's con-tinuation of power ascension up to 50% of full power:
a.
Plant status and equipment operability b.
Management / personnel performance and oversight activities c.
Power Ascension Testing Program adequacy d.
Power Ascension Test Program results e.
NRC inspection coverage and program status 2.
Staf f assessment of licensee performance is as follows:
a.
P,lant Status and Equipment Operability The licensee has determined and the NRC is satisfied that all i
equipment required for continuation of the Power Ascension Pro-I gram is operable. When equipment inoperabilities have occurred, the licensee has generally handled them conservatively and within Technical Specification requirements. Required non-safety l
related equipment is in a condition that supports safe plant operation.
Surveillance tests are up-to-date with no l
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significant identified. discrepancies. The licensee's management review of facility operation up to twenty-five percent power is complete.
Operation of the facility was conducted in a safe manner - and concerns. raised by the NRC and BECo management.
regarding facility operations have been appropriately addressed.
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On April 12, 1989,. at-about 8:45 a.m., the RCIC system injection valves opened unexpectedly. during the conduct of a RCIC logic system functional test. The RCIC discharge check valve failed to seat properly, allowing backleakage of feedwater to the. low.
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- pressure RCIC - suction piping.
This ' resulted in the suction piping relief valve lif ting and. water accumulating on the room floor.
An Augmented Inspection Team' ( AIT) was ' dispatched to
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. Pilgrim to review the cause, safety implications and licensee's
. response to the. event.-
The AIT. concluded that the safety sig-
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nificance of the April 12,1989, pressurization transient. was:
minor' since.several barriers remained intact or available to mitigate the effects of a potential intersystem loss-of-coolant accident.
At. 3:25 a.m.
on May 3, 1989, while licensee personnel were.
troubleshooting the "B" Fee twater Regulating Valve (FRV), the FRV opened unexpectedly, causing reactor water. level to increase rapidly.
This resulted in a turbine trip due to high reactor vessel water level; the turbine. trip caused an automatic reac-tor _ scram on load rejection.
All safety systems responded as expected with the exception of five containment isolation valves which closed.
The plant was at 25% power at the time.
The licensee determined that the cause of the unexpected opening of the FRV was due to malfunction of the valve actuator.
The valve actuator-was replaced. The cause of the. spurious closure of five containment isolation valves was determined to be fail-
. ure of an MSIV control solenoid valve and relay setting drift combined with a voltage transient. that occurred when a fast transfer was initiated from the Unit Auxiliary Transformer to the Startup Transformer after the turbine generator trip.
The licensee's short term corrective actions and planned long term actions to reduce recurrence of a voltage transient during a fast transfer were appropriate.
On June 9,1989, the licensee informed the Restart Staff that, as a result of a lead being lifted-and not restored af ter a surveillance test on May 14,1989, one channel of RCIC area temperature monitoring had been rendered inoperable.
The companion channel, two channels of diverse RCIC steam flow monitoring as well as other temperature and radiation alarms, remained available to provide a moderate level of RCIC steam V
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line leak detection and containment isolation capability. There-fore, the technical significance of this prcblem was minimal.
The condition has subsequently been corrected.
A briefing. on the-event and the results' of a BECo investigation was conducted on June 13 and 14, 1989.
Therefore, the NRC Restart Assessment Panel is satisfied that i
all equipment required for continuation of the Power Ascension -
Drogram is operable.
b.
Management / Personnel performar.ce and Oversight Activities The NRC Restart Staff has continued to monitor management and personnel _ performance on an as-needed, around-the-clock basis since startup. BEco management has been found to be responsive to NRC concerns and performing in a cautious, deliberate manner.
Licensee peer evaluators were observed and.have been providing good feedback to personnel. Operators were generally knowledge-1 able of their duties and plant conditions and management main-tains_an active and effective oversight of operations.
During the AIT inspection, in response to the RCIC overpressure-ization event, personnel performance as well as licensee manage-ment response to the event were reviewed by the AIT.
This event highlighted a n' umber of performance issues which were also identified by licensee management in their event review.
The AIT concluded that although these issues involved problems with several' fundamental operating activities, they were not indica-J tive of broad, programmatic weaknesses in the operating organ-
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ization.
Further, the AIT found that the licensee's internal response to the event was well organized, properly paced and 3
focused and comprehensive in the ide' notification of root cause.
An AIT inspection exit meeting and several teleconferences were held with BECo prior to restart following the AIT. The licen-see's corrective actions were discussed, along with the status of implementation of these issues. Based on the results of this meeting and on the independent inspections by the Restart Staff, those corrective actions were found extensive, timely and appro-priately implemented such that NRC agreed with BEco's restart decision.
The AIT's -report has been issued and has been reviewed by the NRC Restart Assessment Panel.
Enforcement action is presently under consideration by the NRC Staff. An enforcement conference was held on June 19, 1989.
Following the turbine trip / reactor scram on May 3,1989, due to the malfunctioning feedwater regulating valve, the licensee formed a multi-disciplinary investigation team to perform troubleshooting and evaluation of this event.
The licensee aggressively and thoroughly addressed the root causes of the event and implemented corrective actions.
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3 y-Enclosura 1 6
r As a result of its investigation of the June 9,1989, RCIC area
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temperature monitoring event, the licensee identified weaknesses in the performance of an Instrumentation and Controls Super-visor.
The supervisor failed to implement the appropriate jumper /lif ted lead controls and failed to properly communicate system status to the on-shift Watch Engineer. The licensee con-cluded, based on reviews of past surveillance tests and mainten-ance requests, that the problem involved with this event was an J
isolated case, not indicative of a programmatic weakness. Appro-i priate corrective actions have been -implemented. These involve some immediate training and changes to review processes, as well as some intermediate term training enhancements.
The Restart Panel assessed this event to determine if the causes were related to those identified during the April 1989 AIT. The Panel concluded that the causes - of the June 9,1989 event were not related to those of the earlier event and thus were not indica-tive of the ineffectiveness of prior corrective actions.
The NRC Restart Assessment Panel has concluded that licensee management and plant staff performance support proceeding to 50 percent of full power.
c.
Power Ascension Testing Program Adequacy The licensee's Power Ascension Test Program continues to be in place and implemented in accordance with the licensee's commit-ments documented in the December 30, 1988 supplement to Confir-matory Action Letter 86-10.
No significant problems or tech-nical issues are outstanding as a result of implementing this program.
d.
Power Ascension Test Program Results The NRC is satisfied that tests and conditions required to be completed by the licensee during performance of the NRC-accepted Power Ascension Program up to 25 percent of rated power have been completed.
Satisfactory results were achieved during the performance of:
(1) HPCI/RCIC System Testing (2) Turbine-Generator Testing (3) Reactor Mode Switch Functional Testing (4) Reactor Engineering Testing (5) Drywell Temperature Profile Measurements
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L (6) Operator On-Shift Training Activities Testing under item (3) was in direct response to 'the technical issues associated with NRC ' Confirmatory Action Letter 86-10.
Also, the NRC evaluated licensee management and plant staff per-formance-during planned periods of normal operations at about 25% of rated power.
During these periods, licensee management had, as planned, reduced the level of oversight of operations.
1 During one such period, on April 12, 1989, the RCIC system over-pressurization event occurred.
The. licensee performed a thorough evaluation of that event and implemented appropriate carrective actions before.the next plant startup. The_ licensee also developed longer term corrective actions, which are pro-gressing satisf actorily. Another period of normal plant opera-tions and staff evaluations began about May 28, 1989.
The NRC
-Panel has concluded that plant operations are being conducted safely, and, in general, cor.servatively.
The NRC has reviewed BEco's actions on those inspection findings which had potential to impact further reactor operations and found no outstanding issues which would preclude the licensee from proceeding up to 50% of full power.
'e.
NRC~ Inspection Coverage and Program Status The NRC integrated inspection plan covering activities from 25%
to 50% rated power has been approved. The inspection plan and inspection coverage levels are equivalent to those delineated in the Pilgrim Restart Staff Operating Plan dated October 13, 1988, for the Power Ascension Test Program.
There are no open allegations at Pilgrim requiring further inspection.
There are no licensee corrective actions pending which would preclude continued plant operations. Although deliberations are ongoing to establish the appropriate enforcement actions for the April 12, 1989, RCIC system event, and the June 9,1989 event, the licensee has already implemented corrective actions.
Reviews by the NRC Staff indicate that the corrective actions for these events are acceptable and form a reasonable basis to conclude that such events will not recur. Therefore, the Staff concludes that any pending enforcement does not preclude operation up to 50% of
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full power.
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. IV. Conclusion The NRC continues to monitor facility operation and licensee actions in conjunction with the Pilgrim Nuclear Power Station Power Ascension Pro-gram.
The licensee has completed the activities of the Power Ascension Program from 5 to 25% power. BECo has conducted oversight of those activ-ities, assessed performance, and requested agreement from NRC to proceed to the next NRC Approval Point of 50% power. The NRC Power Ascension Pro-gram Restart Inspection Staff has monitored licensee activities and con-ducted an independent assessment of operational training, personnel and equipment performance.
The NRC Restart Panel noted that the licensee approached plant operations in a generally conservative, safety-conscious manner as indicated by on-shif t licensed operator response to the partial loss of offsite power on February 21,1989, (which occurred prior to the last approval point release), and the reactor scrams on March 4 and May 3, 1989. The NRC Restart Panel also noted that the licensee aggress-ively pursued troubleshooting and repair of the cause of the Feedwater Regulating Valve malfunction and the unexpected containment isolation valve closures that occurred on May 3, 1989.
The NRC Restart Panel has also concluded that although the organizational performance lapses that led to the RCIC event on April 12, 1989, involved failures in the conduct of several fundamental activities, they were not indicative of broad programmatic inadequacies in the operations organiza-tion.
The NRC Restart Panel believes that the licensee's evaluation of the event and subsequent corrective actions have been comprehensive and properly focused. In addition, the Panel reviewed the June 9,1989, event regarding the RCIC area temperature monitor and concluded the licensee's corrective actions were appropriate and its causes were not indicative of the inef festiveness of prior corrective actions. The Panel is aware of no outstanding technical or performance issues that would prevent the licen-see from safely operating the f acility during that - portion of the Power j
Ascension Program covered by the next approval point.
I The NRC Restart Assessment Panel has held several meetings and telecon-ferences during the period since March 3,1989, to review licensee per-formance and test program status.
On June 8, 1989, the NRC Restart Assessment Panel convened in the Region I f
Office to review licensee readiness to proceed beyond 25% power.
The Panel reviewed in detail the licensee's assessment and corrective actions taken in response to the RCIC overpressurization event and reactor scram / containment isolation valve closures.
On June 13-15,1989, Panel I
Members reviewed the licensee's response to the June 9,1989, RCIC temperature switch event.
Based on these activities, the Restart Assessment Panel is satisfied that plant operations up to 50% of full power can proceed in a safe and deliberate manner, j
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i(O ;,., g ENCLOSURE 2 Current Status of Emergency Preparedness for the Communities Surrounding the Pilgrim Station Progress continues to be noted in the state of emergency preparedness for Pilgrim in the areas of training of personnel, in the identification and.reso-lution of Reception Center issues, in supplying equipment to local towns, in the active and visible involvement in the review process by the Federal Emerg-ency Management Agency (FEMA), in the conduct of meetings among senior level individuals from all concerned organizations and in the tentative scheduling of a full-scale exercise.
Plymouth has 90 of 91 implementing procedures approved in concept by the Board of Selectmen. For the remaining procedure (School Department), a joint school committee and selectmen meeting was held on June 19, 1989, to review and discuss this pro'cedure.
In Duxbury, all 44 of the procedures have been reviewed by the Department Heads and the review committee and were forwarded to the Board of Selectmen on May 1,1989.. The Board of Selectmen met on May 13, 1939, to review the proced-ures. FEMA attended this meeting.
The procedures were returned to the review committee for further review and comment as a result of the Selectmen's review.
j The' other towns have received a copy of the FEMA technical review of their emergency plan and implementing procedures.
There are no major issues identi-fied and the towns are working to address FEMA comments.
Overall. training continues to progress.
The Commonwealth has been working closely with BECo and the towns to approve lesson plans.
Tc date, 14536 of 27379 hours of training for state, federal and local agencies has been completed.
Progress continues on the Reception Centers.
In Taunton, all equipment is in place and available for use.
Staff has been identified for all Reception i
I Center activities and training is being scheduled.
In Bridgewater, all equip-ment is in the town and available for use at the Reception Center. Staff hos been identified for first shift operations and approximately 50% of second shift operations. The Bridgewater State College Board of Trustees approved the use of the college as a Reception Center.
The Chairman of the Board of 1
Trustees has been empowered to enter into a Letter of Agreement for this use.
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This. agreement has been reviewed by legal counsel, executed by BECo and for-J warded on May 25, 1989, to the Board of Trustees.
In Wellesley, decontamina-I
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tion facilities have been located on the reception center site. There are no major equipment. needs outstanding.
BECo and the Commonwealth are actively working on identifying congregate care facilities as well as additional parking arrangements at Wellesley.
Training 'for Department of Public Works personnel has commenced.
The Commonwealth has submitted.the Public Information Brochure to FEMA for a technical review and has received FEMA comments on this brochure.
The staff has continued to attend planning meetings with town Civil Defense Directors, local elected of ficials, Commonwealth and MCDA Area II officials that discuss the status of off-site emergency preparedness.
Notable among these meetings was a meeting held on March 24, 1989, between FEMA and the Commonwealth Secretary of Public Safety. At this meeting, the Secretary stated that the Commonwealth would continue to work closely with BECo and FEMA to resolve the remaining planning issues. Additional meetings were conducted on May 15, 1989 and May 31, 1989, between FEMA and the Commonwealth Secretary of Public Safety.
Significant issues remaining to be resolved were discussed, and agre'ement was reached, subject to completion of certain actions, on schedul-ing an exercise for the week of October 9, 1989.
A Regional Assistance Com-mittee_ (RAC) meeting was held on May 10-12, 1989.
The plans and implementing procedures were reviewed for Carver, Kingston, Marshfield, Bridgewater, Taunton and MCDA Area II, and the plan for the Commonwealth was reviewed.
The RAC agreed that these documents were essentially complete, well prepared and ready to be exercised. A RAC meeting is scheduled for July 18-20, 1989, to complete the technical review of submitted plans and procedures. ' Additionally, FEMA has been actively involved with the Commonwealth and local towns, attending many meetings and work sessions, as well as the regular weekly planning meetings.
A June 19, 1989, follow-up meeting between FEMA and the Commonwealth Secretary of Public Safety was held.
A topic discussed at this meeting was the distribution of the Public Information Brochure.
When the Commonwealth approves the brochure and authorizes distribution, it will take approximately 6-8 weeks to print and distribute to the public.
The attached emergency preparedness summaries provide the June 2,1989, status of selected emergency preparedness issues for each town surrounding the Pilgrim Station, the Commonwealth and MCDA Area II as compared to the status on Febru-j ary 15, 1989.
The staff provided the summaries to the State and to the re-spective town officials through the Civil Defense Directors of each area and subsequently contacted each official to verify the accuracy of the summaries.
In addition to the opportuni Ly provided for each town or state agency to verify the accuracy of Staf f prerured status summaries, NRC Region I Regional Admini-strator, Mr. William T. Russell agreed to attach to these summaries any addi-tional information submitted by the towns or state agencies which they wished i
to bring to the Commission's attention.
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l CARVER EMERGENCY PREPAREDNESS STATUS AS OF 2/15/89 AS OF 6/2/89 EMERGENCY PLAN FEMA review complete as Carver's corrective AND documented in a letter to action response to FEMA IMPLEMENTING MCDA dated 1/31/89.
comments has been PROCEDURES forwarded to FEMA on 4/28/89.
The Emergency Worker Monitoring and Decontamination Station Facility and staff are not currently in place.
They are scheduled to be in place in July 1989.
I TRAINING 938 of-2183 hours of 1206.of 2198* hours of training completed.
Four training completed.
sessions have been Three sessions have been conducted since 12/9/88 conducted since 2/15/89 and two are scheduled and two are scheduled through February 1989.
through July 1989.
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STAFFING
.23 of 23 first shift Personnel for the operations positions (43 remaining vacancies have of 46 total) and 4 of 4 been recruited but not first shift yet trained.
j administrative positions l
(6 of 8 total) are filled.
EQUIPMENT Emergency worker A pager notification i
decontamination, traffic system has been control and dosimetry identified and ordered.
equipment is delivered There are no other and in place in the town.
identified equipment needs.
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EOC Fully operational.
Fully operational.
- Revised to reflect staffing survey conducted by Carver.
i STATUS REVIEWED BY:
Helen Capello, Deputy Civil Defense
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Director
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1 DATE:
June 8.
1989 By telecon with NRC C.
Conklin.
No comments.
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i DUXBURY EMERGENCY PREPAREDNESS STATU3 1...
b'b
-AS OF 2/15/89 AS OF G/2/891 EMERGENCY PLAN ~
The draft plan has 44 of 44 procedures have Ju(D received FEMA-technical been submitted by the
' IMPLEMENTING review.
38 of 43 committee to the I
PROCEDURES procedures have received' Selectmen.
Additionally, department head review.
the Department Heads have Five procedures remain in submitted an executive draft.
No procedures had summary of the procedures-received Selectmen to the Selectmen.
The review.
Selectmen-met on May 13, 4
1989 to' receive comments-and review the procedures.. At that time j
they returned the procedures to the committee - for ' further review and comment.
TRAINING 521 of.2654 hours0.0307 days <br />0.737 hours <br />0.00439 weeks <br />0.00101 months <br /> of 1031 of 2365* hours of
' training completed.
Four training completed.
15 sessions have been sessions have been conducted since 12/9/88.
conducted since 2/15/89 and four are scheduled
.through June 1989.
STAFFING 17 of 20 first shift 6 of 10 administrative operations positions (21 positions are filled.
of. 40 total). and 0 of 5 There has been no other first shift change.
administrative positions (0 of 10 total) are filled.
EQUIPMENT Emergency worker A pager notification decontamination, traffic system has been control and dosimetry identified and ordered.
equipment is delivered There are no other L
and in place in the town.
identified equipment needs.
l EOC Fully operational.
The Fully operational.
telephone has been accepted, but the town requires training on the systems capabilities.
- Revised to reflect staffing survey conducted by Duxbury.
STATUS REVIEWED BY:
Carl O'Neill, Civil Defense Director DATE:
June 9, 1989 By telecon with NRC C.
Conklin.
Comments l
incorporated.
w-
,d KINGSTON EMERGENCY PREPAREDNESS STATUS
~ AS CF.2/15/89 AS OF-6/2/89 EMERGENCY' PLAN FEMA review. complete as Kingston submitted a M4D documented in a letter to corrective action IMPLEMENTING.
MCDA dated 1/31/89.
response on FEMA comments PROCEDURES to FEMA on April 14, 1989.
TRAINING-697 of 1986 hours0.023 days <br />0.552 hours <br />0.00328 weeks <br />7.55673e-4 months <br /> of 1208 of 2023* hours of training completed.
Six training completed.
sessions have been Seven sessions have been
. conducted since 12/9/88 conducted since 2/15/89 and 0 are scheduled and two are scheduled through February 1989.
through June, 1989.
STAFFING 22.of 22 first shift No change.
operations positions (44 of=44 total) and 5 of 5 first shift administrative positions (10 of 10 total) are filled.
EQUIPMENT Emergency worker A pager notification decontamination, traffic system has been control and dosimetry identified and ordered.
equipment is delivered There are no other and in place in the town.
identified equipment needs.
EOC Fully operational.
Fully operational.
- Revised to reflect staf fing survey conducted by Kingston.
STATUS REVIEWED BY:
Frederick Woodworth, Deputy Civil Defense Director DATE:
June 7, 1989 By telecon with NRC C.
Conklin.
No comments.
i MARSHFIELD EMERGENCY PREPAREDNESS STATUS A
L EMERGENCY PLAN FEMA review complete as Marshfield is reviewing AND-documented in a letter to FEMA comments.
There are IMPLEMENTING MCDA dated 1/31/89.
no major problems noted.
PROCEDURES TRAINING 533 of 2211 hours0.0256 days <br />0.614 hours <br />0.00366 weeks <br />8.412855e-4 months <br /> of 764 of 1951* hours of training completed.
training completed.
15 Three sessions have been sessions have been conducted since 12/9/88 conducted since 2/15/89 and eight are scheduled and none are currently through February 1989.
scheduled.
STAFFING 15 of 19 first shift 27 of 38 operations operations positions (24 positions and 1 of 16 of 38 total) and 0 of 8 administrative positions first shift are filled.
administrative positions (0 of 16 total) are filled.
EQUIPMENT Emergency worker A pager notification decontamination, traffic system has been control and dosimetry identified and ordered.
equipment is delivered There are no other and in place in the town.
identified equipment needs.
EOC Renovations complete and Fully operational.
equipment is in place.
The EOC is fully functional.
- Revised to reflect staffing survey conducted by Marshfield.
STATUS REVIEWED BY:
Richard Aanew, Town Manager DATE:
June 7, 1989 By Telecon with NRC C.
Conklin.
No comments.
I PLYMOUTH EMER2ENCY PREPAREDNESS STATUS
~~
s.
l EMERGENCY PLAN The draft plan had 90 of 91 IPs have AND received FEMA technical received Selectmen review
. IMPLEMENTING review.
51 of 92 and approval in concept.
PROCEDURES procedures have received A joint school committee Selectmen review and and Selectmen meeting is approval in concept.
scheduled for June 19, l
1989 to review and l
discuss the school IP.
Clarifying information.added by Plymouth.
The School Department IP has been approved by the superintendent but not yet approved by two school committees and has not been forwarded to the Selectmen.
Saguish/Gurnet IP has been approved, but the egress issue has yet to be resolved.
A comprehensive special needs survey has not been performed.
The Plymouth Airport has been tentatively selected for use as the Emergency Worker Monitoring and Decontamination Station.
Final approval for use of this facility by the A"rport Manager is pending resolution of i
renovation details.
TRAINING 3265 of 7402 hours0.0857 days <br />2.056 hours <br />0.0122 weeks <br />0.00282 months <br /> of 4216 of 7402 hours0.0857 days <br />2.056 hours <br />0.0122 weeks <br />0.00282 months <br /> of training completed.
21 training completed.
25 sessions have been sessions have been conducted since 12/9/88 conducted through 6/1/89.
and 9 are scheduled No training scheduled as through February 1989.
yet for June.
STAFFING 17 of 22 first shift No change.
operations positions (32 of 44 total) and 2 of 4 first shift administrative positions (2 of 8 total) are filled.
EQUIPMENT.
Emergency worker A pager notification decontamination, traffic system has been control and dosimetry identified and ordered.
equipment is delivered There are no other and in place in the town.
identified equipment needs.
EOC Fully operational.
Ftlly operational.
STATUS REVIEWED BY:
J.
Doualas Hadfield, Director, Office of Emergency Preparedness and Alba Thompson, Chairman, Board of Selectmen.
DATE:
June 7.
1989 By facsimile transmission to NRC C.
Conklin.
Comments incorporated.
4
1 8
4.
.BRIDGEWATER EMERGENCY PREPAREDNE2S STATUS 1
I' AS 0F 2/15/89 AS OF 6/2/89 EMERGENCYLPLAN1
' FEMA review complete as Bridgewater's corrective
~
lAND-documented in a letter to action response to FEMA L,
- IMPLEMENTING; MCDA dated 1/31/89.
comments has been
. PROCEDURES forwarded to FEMA on April 28, 1989. 'The Plymouth County C-Med Radio system, which coordinates movement of ambulances to hospitals within the county, is scheduled for elimination June 30, 1989. This planning issue is being addressed by working on an agreement to' extend funding for the system.
' TRAINING 481 of'1256 hours0.0145 days <br />0.349 hours <br />0.00208 weeks <br />4.77908e-4 months <br /> of 567 of 1124* hours of training completed.
Two training completed.
sessions have been Seven sessions have been conducted since 12/9/88 conducted since 2/15/89 and one is scheduled and none are currently through. February 1989.
scheduled.
EOC STAFFING 19 of 19 first shift No' change.
operations positions (38 of 38 total) and 4 of 4 first shift administrative positions (8 of 8 total) are filled.
EQUIPMENT The majority of traffic A pager notification control equipment has system has been been placed in the town, identified and ordered.
There are no other identified equipment needs.
EOC Fully operational.
The Fully operational.
The town is still awaiting photocopier has been the delivery of a map, a delivered, other status photocopier and is unchanged.
miscellaneous office supplies.
REDEISTION Portal Danitora d311ver;d Tha Bridg watcr Stato
.' CENTERS to town.
College board of Trustee's approved the use of the college for a reception center.
Bridgewater.and BECo attorneys concur on the agreement.
The agreement has been executed by BECo and forwarded on May 25, 1989 to the board of Trustee 's.
- Revised to reflect staffing survey conducted by Bridgewater.
STATUS REVIEWED BY:
Frank JLaher, Executive Secretary DATE:
June 12. 1989 By telecon with NRC C.
Conklin.
No Comments.
l
\\
i TAUNTON EMERGENCY PREPAREDNESS STATUS I
<4 l
JU3 OF 2/15/89 AS OF 6/2/89
)
. EMERGENCY PLAN FEMA review complete as Taunton's corrective
'JuiD documented in a letter to action response to FEMA IMPLEMENTING MCDA dated 1/31/89.
comments has been PROCEDURES forwarded to FEMA on April 28, 1989.
There t
I are no major. problems noted.
1
-1 TRAINING 868 of 2224 hours0.0257 days <br />0.618 hours <br />0.00368 weeks <br />8.46232e-4 months <br /> of 1088 of.2008* hours of' l
training completed.
training completed.-
Nine Three sessions have been sessions have been I
conducted since 12/9/88 conducted since 2/15/89 and two are scheduled and one is scheduled through February 1989.
through June, 1989.
EOC STAFFING 20 of 20 first shift All operations and operations positions (38 administrative positions of 40 total) and 5 of 5 are filled.
first shift administrative positions (10 of 10 total) are filled.
EQUIPMENT.
Traffic control equipment No change.
ordered and received by BECo and additional communications equipment ordered by BECo, with some received.
EOC Fully operational.
Fully operational.
RECEPTION Portal monitors delivered No change.
BEco is CENTERS to town.
Civil Defense negotiating with Taunton Director considers the to establish a reception Reception Center fully center at the Taunton operational.
High School.
A decision will be made at the next scheduled school committee meeting
- Revised to reflect staffing survey conducted by Taunton.
STATUS REVIEWED BY:
Robert Spearin, Civil Defense Director DATE:
June 7.
1989 By telecon with NRC C.
Conklin.
Comments i
incorporated.
l 1
L________.__.
= - _ _ _ _ _ _ _ _ _ -
MCDA AREA II EMERGENCY PREPAREDNESS STATUS
FEMA review complete as -
Revision 7 of the
'AND documented'in a letter to emergency plan, including IMPLEMENTING MCDA dated 1/31/89.
correctivo action to FEMA
' PROCEDURES Procedures to be review comments and submitted to FEMA on letters'of agreement was 2/10/89.
submitted to FEMA on June 5,
1989.
Procedure revision. are continuing.
TRAINING 36 of 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> of
'48 of 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> of training completed.
Two training completed.
One sessions have been session has been conducted since 12/9/88 conducted since 2/15/89 and four are scheduled and two are scheduled through February 1989.
through June 1989.
STAFFING 20 of 20 first shift No change.
operations positions (40 of 40 total) and 3 of 3 first shift administrative positions (6 of 6 total) are filled.
EQUIPMENT Status boards and maps to No change.
be delivered by BEco.
Additional communications i
equipment to be ordered by BECo.
EOC EOC was operational.
BECo to renovate an area Improvement discussions adjacent to the EOC and were underway with BEco.
supply additional equipment.
STATUS REVIEWED BY:
Thomas Rodaer, Director MCDA Area II DATE:
June 7, 1989 By telecon with NRC C.
Conklin.
Comments incorporated.
COMMONWEALTH OF MASSACIiUSETTS EMERGENCY PREPAREDNESS STATUS AS OF 2/15/89 AS OF 6/2/89 EMERGENCY PLAN The emergency plan was All procedures are AND forwarded to FEMA for a drafted and in various IMPLEMENTING technical review on stages of review.
PROCEDURES 1/26/89.
TRAINING This area was not 872 of 2008* hours of reported in detail, training completed.
These numbers reflect supporting state departments.
STA ?FING This area was not All EOC positions are reported in detail.
Zully staffed.
EQUIPMENT This area was not There are no outstanding i
reported in detail, equipment needs, although EPZ and Ingestion Pathway Zone (IPZ) maps need to be updated.
EOC The EOC was fully Pully opers'.iona).
operational.
RECEPTION Wellesley has been All esjva equipment CENTERS designated as the including decontamination northern center.
The facilities and monitoring Commonwealth and BEco are equipment is in place at-working out agreements
%ellesley.
Work is regarding short-term continuing on the proposals to make all installation of utilities centers operational.
f.or the decontamination facilities.
3ECo is working to develop short range plats and procedures for utilization cf Wellesley as a Reception Center.
The Commonwealth and BFCo continue to develop long range plans and procedures.
Training has begun for DPW personnel at Wellesley for introduction and overview.
TRANSPORTATION 2960 of 6000 hours0.0694 days <br />1.667 hours <br />0.00992 weeks <br />0.00228 months <br /> of 3536 of 6000 hours0.0694 days <br />1.667 hours <br />0.00992 weeks <br />0.00228 months <br /> of PROVIDER training complete.
training complete.
Two TRAINING sessions have been conducted since 2/15/89 and one is scheduled through June 1989.
' TRANSPORTATION 35 of 35'lGttorr of Corplcto.
Aft 0r adrquato
, PROVIDER cgr0CO3ntuars co.tplGts.
troheing has baan CETTERSIOF cnd to tha Commonwealth, providId, tha AGREEMENT Commonwealth will conduct a test.to determine the adequacy of these letters.
.PUBLIC
' Commonwealth called.for The Public Information INFORMATION additional town review to Brochure was submitted to BROCHURE be complete by 1/18/89.
FEMA for technical review The Commonwealth will not on March 31, 1989.
MCDA issue the brochure until received FEMA comments on reception center issues June S, 1989 and is are resolved.
currently reviewing theF3 comments.
- Approximate pending compilation of latest training report.
STATUS REVIEWED BY:
Jeffrev HausDRI, Director, Nuclear EsJ'e ty s
and Emergency Preparedness DATE:
2MDe 8.
1989 By telecon with NRC C.
Conklin.
Comments incorporated.
_ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ _