ML20149L914

From kanterella
Jump to navigation Jump to search
Forwards Staff Actions Resulting from Independent SA of Plant,For Info & Appropriate Action
ML20149L914
Person / Time
Site: Maine Yankee
Issue date: 11/20/1996
From: Jordan E
NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
To: Taylor J
NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
Shared Package
ML20148C622 List:
References
NUDOCS 9611220205
Download: ML20149L914 (21)
v • d • e


Text

_ . . . - - - . - . . - . . - . - . - - . _ . -. - ._

Novanbsr 20, 1996 4 @ bo. i,K',

MEMORANDUM T0: James M. Taylor l Executive Director for Operations FROM: 4 Edward L. Jordan. DirectoOriginalSigned by:

p Office for Analysis and Egfgj/ntgg, gogg of Operational Data i i

SUBJECT:

STAFF ACTIONS RESULTING FROM THE INDEPENDENT SAFETY ASSESSMENT OF THE MAINE YANKEE ATOMIC  ;

POWER STATION l l

l Recommendations for NRC staff actions resulting from the independent safety l assessment of the Maine Yankee Atomic Power Station are attacled for your  !

information and appropriate action. These staff actions have been reviewed  !

with the respective offices responsible for implementation. A proposed )

memorandum to transmit these staff actions is contained in the attachment.  ;

If I can provide any additional information or clarification regarding these staff actions, please conti.ct me.

Attachment:

As stated Distribution:

File Center AEOD R/F i IRD R/F EMerschoff EJordan .

Dross l i

DISK /D0r AENT NAME: G:\DEIIB\DEPFILES\D1016\STAF-ACT.MYA T eceiw , copy of this pcument, indicate in the box: "C" - Copy wIo attachment, *E" - Copy wlattachment, "N" - No copy 0FC M '

C D:IRD:AEOD b DD:AEOD D:AE A /'

NAME EdMersckff FJCongel hf DFRoss ELJordanf/[ {

DATE 11//1/96 11/19 /96 I 11/ /96 11/))M96 ,

0;FICIAL RECORD COPY njg

, A c6 l\WO95 $

- I f un

[- 4 UNITED STATES

. g g NUCLEAR REGULATORY COMMISSION )

9 . . . . . ,o MEMORANDUM T0: Frank J. Miraglia. Acting Director. NRR Hubert J. Miller, Regional Administrator. RI David L. Morrison. Director. RES William M. Beecher. Director OPA Edward. L. Jordan. Director. AE0D FROM: James M. Taylor Executive Director for Operations i

SUBJECT:

STAFF ACTIONS RESULTING FROM THE INDEPENDENT SAFETY.

ASSESSMENT OF THE MAINE YANKEE ATOMIC POWER STATION l 1

The required staff actions arising from the Maine Yankee Independent Safety Assessment (ISA) are provided as an attachment to this memorandum. The ISA report, which was previously sent to you, documents performance deficiencies and arobable root causes, together with findings and conclusions which form i the 3 asis for the identified staff actions.

The purpose of this memorandum is to identify and assign responsibility for i generic and plant-specific actions resulting from the independent safety i assessment at the Maine Yankee Atomic Power Station. You are requested to resolve each of the items in your area of responsibility and, if appropriate, identify additional staff actions or revisions to the identified actions based on your review of the report. When more than one office is indicated as responsible, the first office listed has lead responsibility. Based on briefings on the independent safety assessment results. I recognize that l actions to address some of these issues may already have been initiated by the staff.

In view of the importance of this subject. I intend to closely monitor and track the status of each item until final resolution. Within 90 days, please provide a written summary of the schedule and status of each item within your area of responsibility, as identified in the attachment, or that you have additionally identified. Further. I request that you provide a written status report on the disposition of your items (and anticipated actions for uncompleted items) by the first week of January of each calendar year, until all items are resolved. Every effort should be made to resolve these issues promptly. Copies of all status reports should be forwarded to Frank Congel (Director. IRD/AE00) to facilitate AEOD's responsibility for status monitoring.

If there are any questions regarding individual action items please contact Frank Congel at 415-7476.

Attachments: As stated

. . . ~ . - - . - . . - . - . - - _ - - - . - . . - . - - . - . - - - . .

i 1 a _. OFFICIAL' RECORD COPY

! STAFF ACTIONS RESULTING FROM THE INDEPENDENT SAFETY ASSESSMENT

. OF THE MAINE YANKEE ATOMIC POWER STATION i

[ 1. Issue: Adequacy of Analytic Code Validation

' The ISA team noted that the plant specific validation of RETRAN by Maine i Yankee to known industry benchmarks for integral and separate effects

. test data was deficient. This validation is important to assure that the plant-specific a) plication of the code effectively models known physical effects. Tle. team found the NRC requirement for this validation to be vague. The single document which states NRC policy on

this issue is Generic Letter 83-11. " Licensee Qualifications for I

! Performing Safety Analysis in support of Licensing Actions." issued on

February 8. 1993, which states, in part: i l ... some licensees planning to Jerform their own safety analyses

! may not intend to demonstrate t1eir ability to use the code by ,

performing their own code verification. Rather, they plan to rely 1 on the code verification work previously performed by the code j developer or others.

1 3 NRR does not consider this acceptable and each licensee or vendor l who intends to use a safety analysis computer code to support licensing actions should demonstrate their proficiency in using

the code by submitting code verification performed by them. not -

j others.

i Additionally, the team found that the NRC has acted inconsistently j relative to its expectations in this area. In some cases, computer  ;

codes have been endorsed for use with little or no validation accomplished. i Action:

Evaluate the agency's expectations and policy relative to code validation. Develop and issue additional guidance and requirements if appropriate, and develop and implement inspection methodology to verify licensee conformance as appropriate. 1 Generic: NRR/RES)

2. Issue: Adequacy of NRC Review of Analysis Codes The ISA formed an expert panel of consultants with extensive experience 4 in the area of analysis code development to assess and critique the results of the ISA's efforts. The reports submitted by these consultants (attached) included observations and suggestions for improving the NRC's process of reviewing analytic codes.

l

. ~ . . - - .

I y/ .l 2
f r Action

i 1 i Review the attached consultant reports and evaluate the need to make l 3 changes to the existing NRC processes as suggested in the reports.

Implement changes as appropriate. (Generic: NRR/RES) l'

3. Issue: Compliance With Safety Evaluation Reports I

During the. Maine Yankee ISA, compliance with safety evaluation report

] (SER) conditions imposed on the use of analytic codes was verified for i 66 conditions effecting 13 codes. While compliance was confirmed. an l audit trail to assure compliance was not always available, t- necessitating. in come cases, additional analyses to verify compliance.

The team found that the Regulatory status of an SER condition was E unclear. ,

l l- Additionally. the ISA team found that the quality of NRC code reviews .)

! was mixed. This may have stemmed from the fact that there was no j p standard review plan for code reviews. Consequently no guidance or requirements existed for: development of an agreed upon set of l

. identified and ranked phenomena, processes, or key parameters; i validation: code modelling detail: sensitivity studies: or peer review

by experts in the field, Actions

f l

i a) Evaluate the agency's expectations regarding the tracking and  !

, closeout of SER conditions relative to compliance auditability.  !

and reportability. Issue appropriate industry and inspection  ;

guidance as needed. (Generic: NRR) l b) Evaluate the need to develop a standard review plan for code reviews. Develop and issue appropriate guidance. (Generic: NRR) t

4. Issue: Adequacy of Licensing Reviews for Power Uprates The ISA team identified a number of mechanical components for which confirmation of operability at the upgraded power level of 2700 'MW, l could not be confirmed. Additionally, the team noted that documentation i of NRC actions on parameters related to the design and licensing bases for Maine Yankee was not identifiable and retrievable from NRC sources.

Actions:

a) Evaluate the Agency's technical review and approval of the )ower uprates for Maine Yankee in light of information developed )y the ISA team. Take appropriate actions to confirm or rescind approval  ;

of the Maine Yankee )ower uprates approved in 1978 and 1988.

(Plant Specific: NRR) 2 -

I

a i b) Evaluate the Agency's process for-technical review and ap3roval of licensee requested power uprates. Implement changes to t1e

!- process as appropriate. ' Based on the results of this review.

! -determine whether any previously approved power uprates should be 1 reevaluated and to what extent. (Generic: NRR)  :

5 c) Evaluate the need and the feasibilty of establishing an NRC  ;

i licensing and design bases database for all plants to centrally

! collect all documentation necessary to support plant licensing.

Take actions as appropriate. (Generic: NRR)

5. Issue: Clarity and Intent of NRC Safety Guide 1  !

During the ISA review of containment spray system and high 3ressure

! safety injection system net positive suction head (NPSH). t1e team found i the guidance provided by NRC Safety Guide 1. " Net Positive Suction head e

for Emergency Core Cooling and Containment Heat Removal System Pumps." '

issued on November-2, 1970. to be problematical with regard to relying i on containment pressure for assuring NPSH for emergency core cooling and  ;

i containment heat removal pumps.

NRC Safety Guide 1 states "NPSH for emergency core cooling and

containment heat removal system pumps caused by increases in temperature i of the pumped fluid under loss of coolant accident conditions can be accommodated without relidnce on the calculated increase in containment

, pressure." Furthermore it states: " Emergency core cooling and

containment heat removal systems should be designed so that adequate net

! positive suction head is provided to system pumps assuming maximum l expected temperatures of pumped fluids and no increase in containment ,

pressure from that present prior to postulated loss of coolant '

j accidents."

i Maine Yankee asserted that they were not committed to Safety Guide I. t i

Consequently, they assumed containment to be at or above the saturation -

L pressure for the sump fluid temp rather than at pre-accident containment i pressure (nominally atmospheric). The issue of whether or not the

! containment can be assumed to be pressurized at the saturation pressure l

for the sump fluid temperature.should be addressed.

i Action:

l i- Review and clarify the staff's intent relative to relying on containment pressure for assuring appropriate NPSH for emergency core cooling and j containment heat removal pumps. (Generic: RES/NRR) l 6. Issue: Adequacy of the NRC Inspection Program i The ISA team observed that the licensee and NRC staff failed to i recognize and/or a)propriately evaluate degraded / nonconforming i conditions. A num)er of potential operability issues existed; however, j neither the licensee nor the staff aggressively pursued resolution of l

l 3

}

I i

-. - -- - . - . .. - - - . _ - . _ _ _ _ - . - - . . - . . . . . . . ~ . - . . . .

f

i j l the issues. Further although staff ~ inspections and oversight reviews of Maine Yankee conducted prior to the ISA identified significant performance issues. they did not fully convey the broad performance problems and weaknesses identified by the ISA team These issues
- included problems with safety system testing programs, licensee
developed technical specification interpretations, and design basis  ;

j adequacy.

L Actions:

i a) Evaluate the inspection program and inspector training and

guidance with regard to testing programs for safety systems i relative to its scope, rigor, and' analysis of results. Implement
inspection program changes and develop new guidance as

! appropriate. (Generic: NRR) e

! b) Evaluate the inspection program and guidance with regard to review  ;

! of licensee developed technical specification interpretations to assure consistency with the intent of the approved technical  :

i' speci fications. Implement inspection program changes'and develop new guidance as appropriate. (Generic: NRR)  ;

l c) Evaluate the inspection program and guidance with regard to the ,

i assessment of the adequacy of plant design basis including a 1

review of the disposition of significant findings from previous licensee efforts such as design basis documentation or design )

i basis reconstitution programs. (Generic: NRR) l

7. Issue: Adequacy of Agency Expectations Regarding Licensee Performance Li 1

j The ISA relied on the existing aaency benchmark for assessing i Jerformance utilized in the NRC systematic Assessment of Licensee

3erformance Program (SALP). Although SALP category rating definitions.

functional areas, and assessment criteria have evolved over time the

Commission raised questions about the SALP definitions. In addition, a
- number of questions were raised during the October 10. 1996, public i meeting on the ISA findings at Wiscasset Maine.  !

Action:

Evaluate the appropriateness of the existing SALP definitions of i superior good, and acceptable performance in light of the NRC's  !
contemporary expectations for licensee performance. Revise these l definitions as necessary. (Generic: NRR) i i i

i

) 4 4

- - ~ - - -. - . -

l * ,

8. Issue: Cumulative Effect of Operator Workarounds The ISA found that operators at Maine Yankee were required to take

' numerous actions to compensate for weaknesses in plant design. Some of these would require operators to take time consuming manual actions such ,

as donning steam suits and deploying a 350 foot extension cord during significant plant transients. Additionally, the team found that Maine Yankee had been slow to resolve a work allocation issue which appeared to direct the two on-shift senior operators to leave the control room in l - the event of a fire coincident with a medical emergency. The cumulative i effect of all these actions had not been evaluated by the licensee or the NRC.

Current NRC policy which would restrict credit for operator action or define the time which may be available for operators to take action is limited. The staff has typically relied on guidance provided in ANSI /ANS 58.8. " Time Response Design Criteria for Safety Related l

Operator Actions." However, the staff has allowed deviations from this guidance when licensee's have provided empirical evidence that operators can take the required actions within the required time constraints. '

Actions- l 1

a) Evaluate the current guidance and policies with regard to the l cumulative effect of operator workarounds. Develop and issue additional or revised guidance as appropriate. (Generic:

NRR/RES) b) Evaluate the need to develop inspection policy and guidance directed at assessing the cumulative effect of operator workarounds. Develop and issue guidance as appropriate. (Generic:

NRR) 9 .- Issue: Agency Policy Regarding Licensee Design Basis Recovery Efforts The ISA team found that the licensee had identified significant design bases issues involving safety-related systems as 3 art of their Design Basis Reconstitution (DBR) 3rogram. DBR reviews lad been performed in ten functional areas. Anotler nine functional areas had been scheduled, but had been delayed due to resource limitations and priority changes.

These areas included the emergency diesel generator. electrical distribution, and ventilation. The licensee and the ISA team found design weaknesses in each of these areas.

Action:

Evaluate the current Agency policy regarding 1Lensee design basis recovery efforts. Consider the need to require or encourage licensees to accelerate and complete efforts to recover and reconstitute their 5

e j.'t

' l c ' design basis, especially older facilities where some information may be j' missing. difficult to find. or inaccurate.

. (Generic: NRR)

) 10. Issue: Public Involvement'in the Assessment Process I The planning and conduct of the ISA' included' extensive State l' participation through thcee team members, two process reviewers, a five member citizen's group and periodic briefings with the Govenor, a public observation entrance meeting and a public participation meeting to l

convey the findings. However, the~ team received comalaints during the 4

' public meeting and via written correspondence that t1ere was insufficient opportunity for "public participation.'"

f Actions:

a) Evaluate the need to provide guidance for public participation (via a.two part meeting) at the beginning of a review to explain and discuss-the scope and objective of the review. Develop and issue guidance as appropriate. (Generic: AE0D/0PA/NRR) b) Evaluate the need to allow at least one week from issuance of a report to a "public participation meeting" on the findings.

Revise or issue new guidance as appropriate. (Generic: AEOD/NRR)  ;

c) Evaluate the need to make additional copies of the entire report  !

available by sending multiple copies to the local PDR in addition j to Internet access. Revise or issue new guidance as appropriate. j (Generic: AEOD/NRR) '

11. Issue: Licensee Response to the ISA Report The licensee was requested to review the independent safety assessment report and respond by December 10, 1996, describing actions'it intends to take to address tne root causes of the deficiencies identified .in the ISA report.

Action:

Review and evaluate the licensee's response to the independent safety assessment report to determine if it appropriately addresses the root causes of significant deficiencies identified in the report. Prepare an 1 approariate reply for the ED0's signature. (Plant Specific:  !

RI/NR1/AEOD) 6

p D2-I9SS I:OdPti FRCR1 JOHf J MRvItJ. IrJC 509 967 4702 P. 2 q

?. .

- . - /

fI sass O HwN v2nciesen M A R V I N scree:

I N C O R P O R A T E D wesi nichians u n s h i n :e r o n 9o333 September 22,1996 Mr. Jim Wolf Lockheed Martin Idaho Tech. Co.

PO Box 1625 Idaho Falls, ID 83415-3521

Dear Mr. Wolf:

I have completed my review of the independent Safety Assessment (ISA) Team's findings on Maine Yankee's application of their codes to help insure that the facility is operated in conformance with its safety analysis.

The ISAT has done an excellent job is performing its review of Maine Yankee's analysis of chapter 15 transients, the codes used to perform these analyses and the applicability of these codes to the plant transients. They are to be commended for the fine job that they have done in such a short period of time.

They have found, in their review, that the Main Yankee reactor transient safety analysis is very good in the area of fuel setpoint and refueling analysis which involves the Casmo, Simulate-3, Star, Frosstey, Cobra 3C, SCU and Chic-Kin. The analyses performed with these codes is well documented, the codes have been appropriately assessed and validated against appropriate data, the importar.t parameters have been identified and appropriate sensitivity studies hav'e been perfomled for these important parameters. Calculations performed with these codes have a direct impact on the plant's ability to operate efficiently and therefore have a direct impact on the profitability of the plant so there is a large monetary incentive for the utility to invest the time and money in these analyses that is required to do them well. I agree with your findings that the performance of the utility in performing analysis with these codes in very good.

The ISAT has found that the performance of the Utility in the application of cystem transient codes such as GEMINI and RETRAN is less acceptable. These types of transients are performed less often and have less monetary incentive so there is a tendency for the utilities to invest less effort into doing them well. I believe that this is an industry wide problem and not a problem specific to this utility.

The ISAT has determined that GEMINI is applied to very simple transients which do not require much sophistication and that it is acceptable as used in the Maine Yankee transient analysis. I agree that this is the case, however, I believe it suffers from some of the same lack of attention that the more sophisticated analyses performed with

p 22'I996 i : OdPt 1 ' FROt.1 JOHN t MRvIl4 INC 509 967 4702 P. 3 1

4 y

RETRAN suffers from. The ISAT ha'sdetermined that all of the transient analy'ses performed with both GEMINI and RETRAN have been performed in a conservative l manner and that the plant is being operated under safe conditions and can, therefore, continue to operate. I agree with this finding.

However, what I find troubling is that the utility had not done all of the necessary sensitivity studies and code assessment necessary to quantify the amount of l conservatism built into the transient analyses. They assumed that the calculations '

would be conservative with out. demonstrating it. The ISAT questioned the results of some of the analyses and assumptions that went into the analyses, causing the utility to perform additional simulations and sensitivity studies to address these questions. This  ;

resulted in the conservatism of the analyses being demonstrated. The utility should '

have done this on its own. The failure of the utitilty to do this is of concern because it is likely that, in the future, conservatisims will be removed to gain more operating margin and, when this happens, the effects of unknown, non-conservatisms may result in the  !

plant being operated in an unsave manner. The utility should do the necessary sensitivity studies to show that:

1. They understand the important parameters for each transient that they are required to analyze.
2. They understand the sensitivity of transient results to variations in these parameters.
3. They have evaluated each of the codes and the models in those codes to assure that they are capable of addressing the important parameters -i.e. that the codes are applicable to the transient analyses to which they are applied.

The utility should document the work that they have done to demonstrate the above so that it can be reviewed by the NRC and so that the knowledge will be passed on to others as utility personnel changes. The utility has initiated development of a document that identifies the important parameters for each transient as a result of the ISAT's inquiries. I commend this action and encourage the utility to complete this effort. I suggest that they use work that has already been conducted by EPRI in this regard which is documented in the Reactor Safety Support Package (RASP), EPRI NP-4498, Volume 3, May 1986.

The utility has indicated to the ISAT that they rely heavily on the code developer for assessment and validation of RETRAN. I have no problem with this as long as the Utility has the code developer review the Utility's application of the code to assure that it is being applied conectly. Otherwise, the utility should meet the intent of Generic Letter No. 83-11 by demonstrating that it has done sufficient code assessment and sensitivity studies to show it is qualified to perform safety analyses with that code. I suggest that the utility have an independent peer review of its analyses and methodology much as the code developer's do to with the generic code.

The NRC should initiate a plan that will' enforce the intent of Generic Letter No. 83-11 since the utilities do not have a large monetary incentive to do so. This should involve periodic spot checks of each utility to assure that the utilities are appropriately

1 9-22r- I 996 I : 05Pt 1 FROf1 JOHN f1ARv !N. INC 509 967 4702 P. 4

').' -

f, .

i l

l i

l l

I l

performing and documenting analyses and that they are canying out necessary activities to demonstrate that the codes are applicable to the transients being analyzed l and that the important parameters and sensitivity of parameters are understood. The NRC plan should provide incentives to the utility industry to upgrade its analytical tools by facilitating adoption of improved models when deficiencies are found in the existing models.

It is clear from the ISAT's review, that the NRC has not been consistent in its expectations for the utilities. The SERS issued for the same code contains different conditions or limits on the codes use, for example. The NRC should implement a plan to assure that code review's, license applications and SERS are consistently reviewed and issued. This requires having a written plan for conducting reviews, including the identification of transients to be analyzed and the important parameters for each transient. I recommend that the NRC continue to use an independent review team to comment on its review of utilities to assure that intemal organizational pressures do not bias the NRC's judgment with regard to utility license applications.

Sincerely, 7# -

Marvin J. Thurgood  ;

MJT Cc: Norm Lauben. NRC i i

.s

1 g

' TO USE THE MAINE YANKEE TELEPHONE SYSTEM:

To dial an in-house extension dial all four digits.

To dial a corporate extension dial all four digits.

To dial a local number (Bath, Wiscasset), dial 9 plus number.

To dial a long distance number dial 9-1, area code plus number.

Please call Diana Selee, 5600 or Chris Cornish,5637 with any telephone concerns. 1 I

Thank you. I l

l i

4

l July 13,'1996 VOICE VOICE i NAME EXT. MAIL NAME EXT. Mall t i i

ALARA 5207 Boucher, Rene 5601 Adams, Rick 5654 .. . 5654 Bourgoin, Dan 4268 4268 (C) .

Albis John 5129 ...... 1001 Boynton, Dave 4279 (C) .. 4279' Allard, Paul 5127 ... . 1057 5673 (P)

Ames. Dudley 5130 .. .. 1095 Brackett Elsie 4155 (C) .. 4155 i Andrews, Al 5129 .. . . 1003 Brackett. Vern 5151 . .. 5151 i ANNEX 5314 Bragdon, Fred 5123 ... . 5123 I Applebee, Bob 5708 ..... 1065 Braley, Sue 4108 (C) . . . 4108 l Arnold, John 4213 (C) . . . 4213 Brand, Ethan 5661 d

. . 5661 Arn:Id. Stephen 5129 . 1005 Brinkler, Jim 4278 4278 (C) .

ArsInault. Bob 5765 ...... 5765 Brown, Debbie 4126 (C) , 4126 Arcinault, Lenny 5129 . 1128 Brown, J. Stanley 5603 . . 5603 Ash, Daniel 5708 .. 1068 Brown, Jim 5356 f356 Atkinson, Joe 4107 (C) .. 4107 Brown, Mark 5880 5880 Aw;lt, Mark 4172 (C) .. 4172 Brown, Wallace 5601 ... 1073 Bruce. Carel 5372 5372 B: con, Pamela 4120 (C) 4120 Bryant, Bill 5756 .. . . 5756 BAILEY BARN 5216* Bufkin, Jon 5136 . 1023 Bailly, Scott 5143 .... 5143 Burton, Nancy 5386 . . 5386 Briliy, Stephanie 4241 (C) . . . 4241 Busler, Kelly 5128 ... 5128 Bill, Bill 5622 5622 Butler, Alan j

. .. 5351 ... . 5351 Bilmer, Debbie 5172 .... 5172 i

l Binks, Buddy 5682 ... . 5682 Callahan, Matt 5125 . . 5125 ,

Birron. Lee 4177 (C) .. 4177 Capristo, Aldo 5723 5723 l BIrron. Lyndon 5777 .. ... 5777 Card, John 5159 . 5159 I Birry. Bill 5681 .. ... 5681 Carmody, Tom 5130 ..... 1126 l Brrry. Starr 5384 ...... 5384 Caron, Paul 5609 .. . 5609 Brahaw, John 5708 ... .. 1072 Carslick, Jim 5618 .... 5618 BIxter, Bill 5153 ... 1029 Cater, Rena 5700 . . . 5700 i Batsley, Brad 5175 ..... 1038 Cavanaugh, Neil 5381 . . .. 5381 Braulieu, Kathy 4170 (C) . . 4170 Cereste, Paul 4112 (C) . . 4112 Bickham. Alan 5127 .. ... 1049 Chase, Bob 5102 .... 5102 Brckham, Mona 4272 (C) .., 4272 Chase, Martha 4115 4115 (C) .

B; gin, Jitn 5129 .,. 1015 CHECKPOINT (HP) 5135 Bilinger, Krista 4125 (C) CHEMISTRY LAB 5136 BLliveau. Karen 5367 (P) Cheney, Shirley 5193 . 5193 4168 (C) .. 4168 Chipman. Maynard 4152 (C) . 4152 Binner, Rocky 5129 ...... 1129 Christiansen, Steve 5154 ... 5154 BIrgquist. Kerry 5127 .. . 1047 Clifford, Renee 5353 . . . 5353 Birthiaume. Louis 5130 . .. 1079 Clukey, Scott 5207 .. 1042 Bickford, Adele 5150 ...... 5150 CMP 623-3521 Bickford Bob 5196 ..... 5196 Collamore. Dave 4274 (C) 4274 Bickford, Dick 5342 . ... 5342 COLLECTION CENTER 5832 BlIir. Jonathan 5708 .. 1058 COMPUTER ROOM 5101,5133 Bl:ir. Sally 4122 (C) . . . 4122 COMPUTER ROOM 4132 (C)

Bliir. Tamara 5189 CONFERENCE RM 101 4161 (C)

BI ke. Loa 5789 . . 5789 CONFERENCE RM 102 4162 (C)

Bl;il). Ed 5129 . . 1016 CONFERENCE RM 103 4163 (C)

BOARD ROOM (Corporate) 4500 or 4501 CONFERENCE RM 201 4251 (C)

BODY COUNT ROOM 5350 CONFERENCE RM 202 4252 (C)

Boivin, Gerry 5167 . .. 5167 CONFERENCE RM 203 4253 (C)

Bolden. Cart 5867 CONFERENCE RM 204 4254 (C)

BOLTON (508) 779-6711 CONFERENCE RM 206 5305 Boninfant. Art 5115 .. . 5115 CONFERENCE RM NSE 5366 l Bon:nfant, Cynthia 4123 (C) . . 4123 CONFERENCE RM OPIT 5757

! Boucher. Dick 5129 . .. 1006 CONFERENCE RM PED 5648

  • .Denotes Non.DID Numbers a Not Direct Dialable N WCWNNNE-2 ist

4 l;

July 13, 1996

VOICE . VolCE
NAME EXT. MAIL . NAME EXT. MAIL i CONFERENCE RM PLT MGR . 5347 Dostie, Pat (SNSI) 5349 i CONFERENCE RM PORC 5306 Dover, Mark 5139 ..... 5139  !

i - SPEAKER PHONE 5746 Drake. Bill 5186 .... 5186~ ,

J. _ CONFERENCE RM QPD 5808 Drake, John 4180 (C) 'l CONFERENCE RM T.S. 5345 Drottar. Fred 4211 (C) . . 4211  !

CONFERENCE RM 404 5824 Drury, Delinda 4105 (C) . 4105 CONFERENCE RM 406 5821 Dubois. Jason 5130. . . 1116 Connell, Jim .

5733 ...... 5733 Duncan. Rich 5378 . ... 5378 CONTAINMENT ' Hatch 5395* Dunphy, Glenn . 5127 .. . 1055 46'HP 5287* Durgan Ray 5129 .. 1021 El 46 5616* Dyer, Wendy 4189 (C) . . . 4189 El-2 5741*

Loop 1 5291* EllE Lab 5828 Loop 2 5292* Eames, Chick 4212 (C) , . . 4212 Loop 3 5293* EATON FARM 882 7153 Security 5335' Ebert, Peter 5626 .... . 5626-CONTROL ROOM 5130,5131,5132 Edgerly, Susan 5377 . .. 5377 Cook, John 5130 ...... 1098 Egerdahl, Jeff 5147 .... 5147 Cook, Sue 5179 . ... 5179 Eisenhaur, Mark 5130... . 1110 Comish. Chris 5637 .... 5637 Ellis, Henry 5129 ...... 1002

. CORPORATE OFFICE 798-4100 Embry, Ken 5610 .. .. 5610 Cote, Nancy 4280 (C) . . . 4280 Emerick Rod 5365 ... .. 5365 Cox. Ashleigh 5656 EMPLOYEE ASSIST 4179 (C) .. 4179 Crabtree. Jeff 5130 . .. 1099 EMPLOYEE ASSIST 5879 (P) . 5879 CREDIT UNION 2359 (A) ENVIRONMENTAL LAB 5189 4359 (C) Erhard, Lincoln 5130 ..... 1109

- 800-696-1146 Erickson, Dave 5862 . .. 5862 .)

Cross, John 5708 ...., . 1059 Evans, Steve 4203 (C) . . . 4203 Crowder. Dale 5753 ...... 5753 Evringham. Mike 5191 .. 5191 l Crowder. John 5387 .. . 5387 j Cunningham. P.J 5348 ...... 5348 FACILITIES 5175 Curtin. Lois .. 4171 ..... 4171 Fairbanks John 5813 .. ... 5813

~ Curtis, Dennis 5155 ....... 5155 Fales. Neal 4329 (C)

Cushing, Jack 5130 ...... 1120 Farnham Bruce 5130 .... 1106 Cyr, Paul 5726 ... . 5726 Famsworth, Mike 5130 . ... 1078 i Cyr, Roland 5680 ..... . 5680 i

" FAX" D:lton, John 5810 ...... 5810 ALARA 5221 Dalton, Stanley . 5601 ... .. 1077 BAILEY HOUSE 5105 Dandeneau. Tom 5710 ...... 5710 COLLECTION CTR 5841 Otrgis. Dave 5130 ...... 1103 CONTROL ROOM 5877 DARK ROOM 5624 DOSIMETRY 5317 Davis. Walter 5320 ..... 5320 ENGINEERING 4220 Day,Sean 5130 .. 1101 FINANCE 4166 D1Bartolo. John 5829 .. . 5829 HUMAN RESOURCES 4178 Dss.Rodney 5316 ... 5316 INFO CTR 882-6997 Danton. Mike 5113 . ... 5113 LICENSING 4230 DsRuiter. Hank 5816 .. .. 5816 LOBBY-CORPORATE 4101 Dishl, Leann 4199 (C) . .. . 4199 MAINTENANCE 5892 DiPierro. Mark 5304 ..... 5304 MEDIA CENTER 882-4139 Dixon. Julianna 5770 ...... 5770 .OCC 5392 DOCUMENT CONTROL 5193 OWCC 5783 Doiron. Ron 5130 .. .... 1122 PLANT MGMT 5859 Donaldson. Wendy 5602 . .. 5602 PUBLIC AFFAIRS 4194 (C)

Donatelle. Emery 5327 . . . 5327 PURCHIFINANCE 4114 (C)

DOSIMETRY 5170 QPD/ ENGINEERING 5313

  • . Denotes Non-OlO Numbers = Not Direct Dialable N WCWNPMCNE 2 m
u. __ __ - ,_ _.- .- -- - .

July 13, 1996 VOICE VOICE l NAME EXT. Mall NAME EXT. Mall l e STAFF BLDIADMIN 5177 Greene, Linda 5399 . 5399 Greenleaf, Bruce 5129 . . 1010 FAX (continued) Grifnn, Anne 5318 . 5318 SECURITY Staff Bldg 5358 Griffin, Bryan 5127 1050 APS - Plant 5861 Grimard, Larry 4345 (C) . 4345 TECH SUPPORT 5107 Grotton, Doug 5728 . . 5728 WAREHOUSE 5625 Grover, Darryl 5130 1115 Guerrette, Carrie 4184 (C) 4184 F;rdinand, Cathy 5717 . . 5717 Guiou. Diane 4167 4167 Finn, Martha 5368 . .. 5368 FIRE PUMP HOUSE 5116' Haggett, Craig 5303 . 5303 FIRE TRAINING SITE 882-6890 Hahn, Debra 5745 5745 F!RST AlD 5119 Haines, Mark 5130 . 1119 FISSION CHIPS 882-9541 Hall, Sherrie 4186 (C) 4186 5223 (P) Hall, Tom 5130 1121 Fluit. Dana 5691 . .. 5691 Hamel Rick 5843 5843 Forbes,Ian 5744 .. 5744 Hanley, David 5127 . 1054 Fortier, Monica 4284 (C) . . . 4284 Harding. Laurie 5192 . 5192 Folter, Roland 5601 . . 1046 Harvey, John I 5782 .. 5782 Fox Eric 5708 .. . . 1069 Haskell, Bonnie 5740 . 5740 Fox Tom 5130 . .. 1080 HasMns. Bob 5858 5858 Foye. Steve 5175 .. . 1034 Haslam, Janeth 5632 . 5632 Fr: win, Wes 4296 (C) . . 4296 Hathaway, Bob 5853 . 5853 Frizzle. Charles 4141 (C) . 4141 Hayes Greg 5127 . . 1048 Frothingham, John 4340 (C) . . 4340 Hayward, Bob 5321 5321 5820 (P) .

Hayward Gerald 5130 . . 1094 Furgen. Linda 5108 . . . 5108 Healey, Linda 5371 . 5371 Heath Carla 5666 . 5666 Gabriele, Mike 5130 . ... 1111 Heath, Ellen 5663 5663 Gagnon. Richard 5130 .. .. 1093 Hebert, Chad 5377 G:mache, Paul 5175 . 1035 Hebert, Jim 4285 (C) . . 4285 Gann. Bob 5708 . . 1062 HELP DESK 4281 (C) . 4281 Grnnon, Judie 4169 (C) . 4169 HELP DESK 5281 (P) . 5281 Grreeau. Robert 5129 . 1014 Hendricks, Mary 5879 (P) . 5879 G; spar. Brian 5163 . 5163 4179 (C) 4179 GATE HOUSE 5109* Hewison. Bruce 5129 1019 Grorge John 4188 (C) . 4188 Hickey, Debra 5651 ... 5651 G:rmer. Len 5130 . . 1081 Hickey, Dennis 5379 . . 5379 Gifford, Tedd 4207 (C) .. 4207 Higgins. Bob 5667 . . 5667 Giggey.Clayton 5604 ... . 5604 HILL, DR. D 443-6211 Gilpatrick. Hunter 4205 (C) . . 4205 Hill, Nancy 4121 (C) 4121 Glidden. Glen 5127 .. . 1053 Hill, Scott 5627 5627 Glidden. Tracy 5815 . . 5815 Hinckley. Bud 5882 5882 Goggin. Don 5346 5346 Hinkley, Mark 5708 . 1064 Goodall, Ken 5130 . . . 1083 Hoepner. Karen 5195 5195 Goodeill. Todd 5388 . . . 5388 Honaker Carol 5870 5870 Gorman Gloria 4157 (C) . 4157 Hope. Barbara 4148(C) 4148 Gould. Steven 5130 . . 1082 Howard. Murray 5130 1091 Gow. Charlie 5237' . . 1075 Howard. Ron 5881 5881 Granholm, Ethel 4219 (C) . 4219 Howe Stephen 4187 (C) 4187 Grant. Joe 5137 .. 5137 Howes. Eric 4195 (C) 4195 Grant. Ron 4256 . 4256 Hoxie Greg 5130 1102 Gray, John 4341 (C) .. 4341 HP CAL ROOM 5710 Gr:en. David 5130 .. 1105 HP CHECKPOINT 5135 Grzen. Kevin 5662 ... 5662 Huber Mike 5352 5352 Grrene. Julie 4242 (C) .. 4242 Huff. John 5130 1123

  • Denotes

- Non-DID Numbers a Not Direct Dialable N WoWNPHCNE-2 m

July 13, 1996 .

VOICE VOICE s Mall EXT. MAIL NAME EXT.

NAME s

Hulburt, Dave 5153 .. . 1030 Lord, Troy 5769 Hummer, Jim

. 5312 . . 5312 Love, Katie 5364 . . . 5364 Hurley, Claudia 5787 .. ... 5787 Lovejoy, Herman 5129 . 1011 Hurley, Nadine 4165 (C) .. 4165 LOW LEVEL WASTE BLD. 5232*

5127 Lydon, Pat 4164 (C) .. 4164 I & C SHOP 1 & C TRAILER 5203* Lynch, Marv Ann 4192 (C) . 4192 INFO CENTER 5740 1-800-458-0066 Maben, Jerry 5893 .... . 5893 5836 MacDougall, Don 5891 5891 INTERVIEW ROOM (Plant)

MAILROOM-CORPORATE 4123 Jacovics, Scott 5234 MAILROOM-PLANT 5128 Jameson, Bud SF,52 ..... 5852 MAINTENANCE 5666 JANITOR'S ROOM 575? Cold Side Shop 5176 J;nnings, Ken 5863 . 5863 Hot Side Shop 5707 J:wett, Larry 5130 .. ... 1031 MWCC 5339 Johnson, David 5657 ... .. 5657 Print Room 5284 Johnson, Eric 5630 . 5630 Maloney, Bob 5844 . 5844 Johnson. Lori 4150 (C) . . . 4150 Marchio, Roni 4156 (C) .. 4156 Johnson, Walter 5636 .. ... 5636 Marshall. Glenn 5718 .. .. 5718 Jonts, Deb 5175 .. ... 1040 Marstaller, Tom 5183 . . 5183 Jonts. Howard 4244 (C) . . . 4244 Marston, Matt 5857 . 5857 Jordan. Bob 4243 (C) . 4243 Martin, Barbara 5170 . 5170 Jordan, Tony 4103 (C) . . 4103 Martin, TJ 4201 . . . 4201 Mason. Andy 5686 . 5686 Kerina, Tom 5634 . . . 5634 Mathieu, Jim 4263 (C) 4263 Kich, Frank 5130 . . 1097 Mathieson, John 5144 . . 5144 Kimball. Blaine 5329 ., ... 5329 Matthews. Merle 5129 . .... 1007 Kingsbury, Mark 5129 ... .. 1012 McAllister, Scott 4343 (C) . . 4343 Kirsch, Jon 5198 . .. 5198 McCabe, Lee 4202 (C) 4202 KITCHEN 4305 (C) McCarron, James 5130 ... 1117 Kisin. Fred 5619 .. 5619 McCrossin. Dick 5606 . 5606 Knobel. Lisa 5605 ...... 5605 McDougold. Danny 5138 . 5138 Knobel. Stephen 5798 .... . 5798 McGrath, Rick 5302 . . 5302 McGregor. Brian 5130 .. 1113 Labbe. Bill 5130 ..... 1085 McGuire, Bob 4138 (C) . 4138 -

Lach, Walter 5382 . ... 5382 McInnis, Mark 5130 1112 Lrits, John 5768 ..... 5768 McKenna. Dina 5729 .... . 5729 Lamarre. Jane 5652 . ... 5652 McMahon, Dan 5190 .. . 5190 Lengdon. Tom 5136 . .. 1022 McNally, Dana 5130 1107 LaPointe. Arnette 416" (C) . . . 4160 McNally, Jeff 5130 . . 1108 Lauterbur, Douglas 5341 . ... 5341 Mehlhorn. Peter 4346 (C) 4346 Layton. Roxanne 5175 .... . 1037 Meirell, Bob 5834 .. 5834 Lstvitt. Nancy 4116 (C) . 4116 Mercer, Dennis 5895 5895 LiClerc Steve 4342 (C) 4342 Merry, John 5720 . . 5720 Lie, Barbara 4185 (C) .. 4185 Metivier, Paul 5613 . 5613 Lih:uillier. Gerry 5141 .. . 5141 Michael, Colin 5175 1039 Liighton. Gardner 5175 . .... 1041 Michaud. Andrew 5130 . 1090 Liitch. Graham 5800 .... 5800 MICROWAVE ROOM 5614 Lemieux, Dan 5126 ... .. 5126 Minott. Marshall 5130 1089 Lsonard. Brian 5724 . .. 5724 Mitchell, Paul 5130 . 1124 Lavssque. Mark 5849 . 5849 MONTSWEAG PP. HSE 882-6327 Lewis, Donna 5692 . . .. 5692 Morang. Louise 5119 (P) 5119 Liscomb. Rick 5184 . 5184 Mornson, Scott 5180 . .. . 5180 Lloyd, Christopher 5689 . . 5689 Mortimer. David 5737 5737 Loon, Lewis 5819 . .. . 5819 Moulton, Brent 5181 . . 5181 Lord. Bruce 4259 (C) . 4259 Movafegh. Hassan 4297 (C) . 4297

  • .Denotes Non-DID Numbers = Not Direct Dialable N WCM4P%NE 2 m

1 July 13, 1996 i

VOICE VOICE  !

NAME EXT. Mall NAME EXT. Mall l Munn, Valmon 5732 ... 5732 Pleau, Cherry 4197 (C) . 4197 l Plummer, Brett 5153 . 1033 l Newcomb, Peggy 5104 . ... 5104 Portela. Bill 5655 . 5655 l Nichols, John 4270 (C) . 4270 Potteiger, Debra 5207 1043 Nichols, Steve 42f0 (C) 4260 Pratte, Steve 5760 . 5760 Nile:. John 5164 ...... 5164 Prior, Brenda 5369 . 5369 Nolan, Mary 4198 (C) .. 4198 Proctor, At 5152 .. 5152 l Norton, Wayne 5886 . . . 5886 PSS 5153*

Norton, Steve 5779 . 5779 NRC 5120 QPD WAREHOUSE 5336.5696 Nuzzo, Keith 5%3 5885 Qualey, Jason 5102 O'Brien, Craig 5338 . .. 5338 Radasch, Rocky 5124 5124 O' Brion, Mike 5866 . 5866 Radsky, Pete 5134 5134 O'Cliir, Roger 5189 . . 5189 Readinger, Mark 5669 5669 Oliv:r, Marylou 4223 (C) . 4223 Reed, Dick 5129 .. 1018 Ols:n. Heather 5601 .. . 1127 Regan. Dan 5719 . 5719 Om: tick, Doug 5887 . . 5887 RELAY HOUSE 5117,5118 O'N:il. Ed 4136 (C) . . 4136 RESOURCE ROOM 5716 5262 (P) Richards, Mark 5804 5804 OPIT 5192 Rines. Bob 5601 . 1076 OPS BRIEFING ROOM 5705 Rines, Marlene 5788 . . 5788 OPS CONTROL CENTER Rivard, David 5722 5722 (OCC) 5361 Roberts, Mark 5375 5375 OPS TRAILERS Ross, Al 5178 Crew A - 5884 Ross. Art 5197 .. 5197 Crew B - 5853 Ross, Dave 4271 (C) . 4271 Crew C - 5331 Rossignol. Tim 5130 1088 Crew D - 5762 Rowe, Chet 5727 5727 Crew E - 5897 Russell. Pete 4176 (C) 4176 Crew F - 5898 Russell, Tim 5848 5848 Crew G - 5896 Rydzewski Heidi 5360 Ouillette. Dave 5136 . 1025 Ou llette. Steve 5708 .. 1060 Oulton. Dick 5129 .. . 1008 Sabins. Duane 5708 1071 Oyster. Donald 5171 .. 5171 Saleeby, Joel 5130 , 1087 Salib, Andrea 5708 . 1070 Packer James 5817 . .. 5817 Salter, Bryan 5136 . 1027 Pedivana. Barb 4143 (C) .. 4143 Sanoski, Jim 5846 5846 Pa"; g. Alex 5701 .. . 5701 Scheidegger, Mike 5328 . 5328 Parus. Paul 5127 ...... 1051 Schmidt, Richard 5838 (P) 5838 Parker. Arnold 5301 . 5301 Schmidt, Beth 4291 (C) . 4291 Pazdziorko. Emil 5827 . 5827 Schoppmeyer. Bill 5136 1024 P;i. Kerlin 5363 ... 5363 Schubert. Bill 5187 5187 Pe:rson. Phyllis 5601 1045 Schwan, Jim 5875 5875 P;lletier, Dave 5130 . . 1084 SECURITY (PLANT) 5157 P:lletier. Donna 4191 (C) .. 4191 SECURITY TRAILER 5854 P;lz;r. Paula 5330 .. 5330 Selee. Diana 5600 . . 5600 P:ndagast. Don 5130 1125 Selee. George 5629 . 5629 P nney. Rod 5750 . 1009 Sellers. Dave 5621 5621 P:t;rson. Walter 5165 . 5165 Setchell. Frank 4111 4111 (C)

P;rry Steve 5345 . 5345 Sewell, Wayne 5847 . 5847 Piirce Jill 4149 (C) . 4149 Shaw, Chris 5185 . 5185 Pillsbury. George 5166 5166 Shea. Rick 5840 5840 PLANT SERVICES 5175 Shean, Art 5385 5385 Plante. Paul 4206 (C) . . . 4206 Shelanskey, Steve 5823 5823

  • .Denotes Non-DID Numbers = Not Direct Dialable N ucMMP**CNE.2 tot

l l ,

July 13, 1996 VOICE VOICE i NAME EXT. MAIL NAME EXT. Mall o

l SHIFT ENGINEER 5343 ..... . 534 Vogel, Terry 5130 . .. . 1032 I l

Shippee, Tom 5759 .. . . 5759 Vogt, Bethany 5381 1 Si:rcks, Harold 5725 ...... 5725 )

SIMCOM 5397,5398 Waldman, Joe 5690 . . 5690 l Simmons Willy 5615 .. ... 5615 WAREHOUSE 5601 l Smith, Larry 5865 ...... 5865 Waterhouse, Brian 4269 (C) . . 4269 Smith, Steve 5676 .... . 5676 Weast, Jim 4231 (C) .. 4231 Smith, Steven R. 5130 .. . . 1114 WELDING LAB 5322 l Smith, Will 5162 . . .. 5162 West, Greg 5601 ... . 1074 Snow. Bob 5684 ..... 5684 White, Steven 5207 1044 SOS 5132 White, Terry 5130 . . 1104 Soule Dennis 5153* ... 1028 Whittier, Doug 4273 (C) . . 4273 Soule, Derek 5779 Wicks, Wayne 5623 . 5623 l S:ule. Eric 5698 5698 Williams, Gretchen 4146 (C) . 4146 Sp:ulding, Bob 5708 . 1067 Willoughby, Paul 5311 5311 ,

Spied,Jud _ 4282 (C) . . 4282 Wills, Bob 5668 . . 5668 i Spinney, Cathy 5393 ... .. 5393 Wills, Lori 4110 (C) . . 4110 STA 5343 Wilson, Paul 5136 .. .. 1026 St2vens, Bob 5129 . . .. 1130 Winicov, Herb 5695 .. . 5695 i Stsvens, John 5693 ...... 5693 Winslow. Dana 4147 (C) . 4147  ;

Stivenson, Don 5390 ., . 5390 Withee, Ginny 5169 . 5169 1 St: wart, Garry 4344 (C) .. 4344 Wood. Mary 5677 . . . , 5677 ,

Stimpson. Art 4159 (C) . . . 4159 Woodhams, Phil 5127 . 1052 l STOCKROOM (Plant) 5151 Woodward, Craig 5617 .. . 5617 Stover, Pat 4113 (C) .. 4113 WORD PROCESSING 5700,5172.5870 Stover, Paul 5708 . .... 1066 Wyman, Michelle 5714 . .. 5714  !

Stowers. George 5749 . ... 5749 Wyman, Elmer (Skip) 5175 .. . 1036 Strickland, Sandy. 4154 (C) .. 4154 Wytas, Jake . 5818 . 5818 Stuart, Don 5129 1020 l

Sturgis, Dana 5868 ..... 5868 Young, Cliff 5708 . .. . 1061 Sukeforth. Scott 5876 .... 5876 Suthambhitak, Viroon 5767 . .. 5767 Zehler, Dan (CE) 5145 Sw:nton, Deborah 5381 882-6951 Sw rtz. Mike 4240 .. .. . 4240 Zhu,Yong 5650 .. 5650 SWITCHBOARD (Plant) 5780 Ziemann, Van 5736 . . 5736 j SWITCHBOARD (Corporate) 4100 Taylor, Jim 5683 .. .. 5683 Traylor, John 5103 . . 5103 EMERGENCY OPS. FACILITY l Tsmple. Bruce 5110 .... 5110 EOF Manager 5641*

Temple. Jeff 4227 (C) .. 4227 Rad. Assess. 5640*

Thiboutot. O.) 5628 ..... 5628 Dose Proj. Coord 5639*

Thomas. Micky 4181 (C) .. 4181 Manpower Coord 5602*

Thornburg. Larry 5631 ...... 5631 Security Coord 5769*

Tibbetts. Candy 5649 ...... 5649 State Rep 5730*

Tibbitts. Dean 5738 ... .. 5738 Timblin. Daniel 4328 (C) OPERATIONAL SUPPORT CTR.

Torberg, Herb 5319 . .. 5319 OSC Manager 5307*

Tr cy, Bill 5315 ... 5315 Rad. Controis 5308'

, Twickler. Jeff 5130 ...... 1096 l

TECHNICAL SUPPORT CTR.

! VAULT 5702 TSC Manager 5647*

i Vautour. Larry 4153 (C) .. 4153 TSC Maintenance 5731*

Vailleux, Mike 5344 .. 5344 Vircoe, John 5309 .. .. 1004 EMERGENCY DIRECTOR 5648' VISITORS CTR. 5740

  • -Denotes Non DID Nurnbers = Not Direct Dialable N WoMWe<NEht

July 13, 1996 VOICE VOICE l NAME EXT. MAIL NAME EXT. Mall l 1 DAILY UPDATE 800-762-7104 CONTRACTORS PACING - PLANT (From Plant / Corporate)- ABB -Dan Zehler 5145 l Dial 60 - ALL 882-6951 61 - PLANT 62 - STAFF BLDG. APS Security 5635 Access Control 5109*

i PAGING - CORPORATE (From Plant) Administration 5635 l 4064-ALL CAS 5158 4065 -1st FLOOR (ADMIN /PURCH/ FIN) SAS 5157 066 -2nd FLOOR (LIC/CED) Chief Urquhart 5146 .. 5146 Training 5878 PACING - FROM BOLTON Tunnel- 5357 1 To plant - 853-6000 '

To corporate 854-4064 Bartlett 5135 YANKEE NETWORK CALLING: Burns and Roe 5244,5373 I 882-4270 BOLTON 8-856-XXXX Fax 882-8017 ROWE 8-852-XXXX VERMONT 8-851-XXXX Cianbro 5734,5735

)

i BRATTLEBORO 8-855-XXXX 882-9843 l SEABROOK 8-858-XXXX l MANCHESTER 8-859-XXXX Commoletti, D. 5222 1 WESTEORO 8-857-XXXX l Downs Associate j Dial d + 8XX-0011 if extension is not known. Steve Downs 5310 VOICEMAIL ACCESS Facilitators i From Plant to Corporate dial 4200 then mailbox number Mike Desroches 5269*

From Corporate to Plant dial 5100 then mailbox number Rod Sweet 5271*

Steve Themault 5272*

Ross, Art 5199 Sargent & Lundy Walt Smith 5241 Simms, Bill 5222 United insulation 5864 Yankee Carter, Jack 4332 (C) . 4332 Cloutier, Bill 5778 (P)

Fucito, Dom 4334 (C) 4334 Jones Bill 4331 (C) . 4331 Lozano,Lu 4335 (C) . 4335 ,

McArdle, John 5310 (P)

McCann, John 4237 (C)

'* Denotes

- Non4tD Numbers = Not Direct Dialable N ucump%NE 2 's

l July 13,.1996

, v VOICE VOICE NAME EXT. MAIL NAME EXT. MAIL i

I Oliver. Bob 4336 (C) .. 4336 Sheldon, Pat 4337 (C) . . . 4387 Springer, Todd 5748 (P)

Sullivan, Bill 5391 R: racking Project l

Paul Plant 5806(P) 4206(C)

Dan McMahon 5190(P)

Jack Hurley 5685(P)

Wayne Norton 5886 Charlie Allen 5685

- Rust Trailer 5219,5182 Spent Fuel Pool 5112 Mrine Yankee ISA Team (4th Floor - Staff)

Doug Whittier 5855 Bob Blackmore 5161 ,

St ve Nichols 5380 J:hn DaRon 5810

! - Matt Marston 5857 .

Rocky Radasch 5124 l St:ve Frantz 5359 Peggy Newcomb 5671 Fax 5374 J:hn Frothingham 5820 Julia Greene 5326 .

B:b Jordan 5394

. Bruce Hinkley' 5607 Jim Weast 5699 i

Adile Bickford 5664 l

Ron Grant .5396 Lu Lozano 5739 St:ve Guthrie 5687  :

Pit Sheldon 5839 j l- Judd Speed 5883  ;

Rod Dee 5822 Library 5258 .

ClIrks 5273,5274 Donna Pellitier 5258 Judy Gannon 5825 Lori Wills 5275 ,

Glenn Collins 5367 ChIrry Pleau 5764 Dibbie Brown 5254 P mela Dahl-Newsome 5833 l Micky Thomas 5763 Censultants:

Harry Kister 5178 David Kunsemiller 5672 -

Warren Peabody 5894 i

  • .Denotes NonalO Numbers = Not Direct Dialable N uoM4 PHONE 2 4t
  • DEPARTMENT /SECTIORI NAME EXTENSION AREA - r MANAGEMENT SUPPORT Anna Griffin 5318 e (4th Floor - Operational Support)

PLANT ENGINEERING Adele Bickford 5150 (1st Floor. Staff Bldg.) Wendy Donaldson 5602 QUALITY PROGRAMS (1st Floor. Staff Bldg.) Mary Wood 5677 TRAINING Karen Hoepner 5195 (3rd Floor. Staff Bldg.) Susan Goggin 5360 PLANT MANAGEMENT (Front Office. Plant) Sue Cook 5179 INFORMATION CENTER Bonnie Haskell 5740 FACILITIES / PLANT SERVICES Cathy Spinney 5393 (2nd Floor - Plant)

TECH SUPPORT / RAD PROGRAMS / CHEMISTRY / Jane Lamarre 5652 I COMPUTER (3rd Floor - Plant)  !

RAD CONTROLS - PLANT HP Brenda Prior 5369 MAINTENANCE Carla Heath 5666 PLANNING / OUTAGE / SCHEDULING Laurie Harding 5192 SECURITY,(1st Floor. Staff Bldg.) Dina McKenna 5729 OPERATIONS Carol Bruce 5372 (2nd Floor Staff Building) Nancy Burton 5386 DOSIMETRY Barbara Martin 5170 CHEMISTRY Starr Barry 5384 REACTOR ENGINEERING (4th Floor, Staff Bldg.) Dale Crowder 5753 CORPORATE OFFICE (MAIN SWITCHBOARD - 798-4100)

ADMINISTRATION Sally Blair 4122 BENEFITS Kathy Beaulieu 4170 CORPORATE ENGINEERING Ethel Granholm 4219 HUMAN RESOURCES Judie Gannon 4169 EXECUTIVE MANAGEMENT Barb Padavana 4143 ACCOUNTING Roni Marchio 4156 PURCHASING Lori Wills 4110 FINANCE / TREASURY Nadine Hurley 4165 LICENSING Julie Greene 4242 LEGAL / INTRNAL AUDIT Donna Pelletier 4191 PUBUC At . i Cherry Pleau 4197 Mary Nolan 4198 CENTRAL MAINE POWER MAIN SWITCHBOARD 623-3521 Denotes Non-DID Nurnbers = Not Direct Dialable N WoWNPMCNE 2 m 4

- -- ----a , , - -,-

Retrieved from "https://kanterella.com/w/index.php?title=ML20149L914&oldid=2973614"