ML20155F897
| ML20155F897 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 10/20/1987 |
| From: | Blume M NRC OFFICE OF THE GENERAL COUNSEL (OGC) |
| To: | Paton W, Wessman R Office of Nuclear Reactor Regulation, NRC OFFICE OF THE GENERAL COUNSEL (OGC) |
| Shared Package | |
| ML20151H280 | List: |
| References | |
| FOIA-88-198 NUDOCS 8810130412 | |
| Download: ML20155F897 (43) | |
Text
{{#Wiki_filter:. October 20, 1987 t01T TD: Di ck We s sten, >+R bi l l Pa tm, OCC FMi: Mike Blure, CEC S.BJECT: AniSPim v. MC (Pit.CRIM 1ST CIFQJIT CASE) Enclosed is a first cut of ht is krom as a "Certified Irdex of the Record," to be shittM to the Coart of Ameals m Noventyer 10, 1987. The "Record" In this case is dat was placed before tE Agency ty the , pe t i t t or.a r s , and ea t eve r e l s e the Ag ency re l i ed tpon. The attached list
~ the "Ce r t i f i ed I rcex" ~ I s a conpl e t e l i s t i rg o f a l l do<.uten t s enc l osed with or cited by the Petitlen and the Director's Deelslon. The acNantage of the certified Index is that we don't have to burden the Court with trnecessary docurants. Unforttnotely, though, the Cmmission Secretary, to will certify to the Court that the Index represents the record, nust have all of the docutants that are listed. Accordirgly, I'm recptstirg that you go over the list, and provide to nu ASAP, capits of all of the l isted docunents that M have. Please note for nu Alch ones we do not i
have. To the extent w dco't have them, it's probably safe to asstine that
! w dlWt consider them or rely upon them, and thus they'll be deleted frcm ,
j { the list. Also, please ecM to the list (and provide to nu) arry docuTents that w cmsidered or relled Lpon, tut elch wre not cited. Mary tharks for your contiruirg assistance! ! j
Enclosure:
As stated ! i ' 4 . i 4 I l i i 6G10130412 0G0907 PDR FOIA i l JOHNSONGO-198 PDR
\ . I 1
I Historical seq ence of Pilgrim Offsite Issues t. 6/16 Director of MCDA submitted State RERP (for Pilgrim) to FEMA with staterent that the plan was adeounte. 10/8' /EMA and RAC reviewed and reported on the Massachusetts RERP. PCDA revised the RERP based upon FEtiA's comments. ! 3/3/89 Annual exercise, FEMA observed; six deficiencies identified, t 6/3/82 FEMA held a public neeting. ,The following issues were raised by the public: j Ability to evacuate corrnunities within the 10-mile FPZ Ability to evacuate Cape Cod beyond the 10-mile EPZ Reliability and effectiveness of sirens , Training of teachers, school bus drivers and hospital ) personnel Public infomation brochures
- XI colicy
- i Procedures for elderly and special needs persons 1 o no date Cornonwealth responded to all the above issues by statino the RERP addressed these concerns and pledging to work towards further plan igrovement.
9/29/82 FEMA issued Interim Finding for Pilgrim; first FEMA evaluation; interim finding that State and local response is adequate. 72 deficiencies noted, 13 considered significant. 6/?9/83 Annual exercise. FEMA observed; State and local response is adequate; 15 deficiencies noted. 8/15/84 Drill, FEMA observedi State and local response adeouste; one deficiency noted. ! 3/85 Status of offsite RERP was: Many planning problems unresolved from 10/81 RAC review .
- j Comenwealth had not responded to 9/82 RAC review Comonwealth had not provided FrMA with schedule of i corrective .ctions for problems 'de9tified in 1982 and 1983 exercises {
3/6/85 FEMA suspended processing of Comonwealth request for 44 CFR 350 approval. _ _ . = . 7 .. .__
. l
-?-
1 6/20/85 Connonwealth sent a schedule to FEMA delireating st(ps to be taken to correct 19P.2 and 1983 exercise problems. These revisions were not delivered to FEMA. 9/5/85 Annual exercise, FEMA observed; interim finding + hat State act local response is adequate; 4 deficiencies noted remedial drii; plarred for October 29, 1985.
)
10/?9/85 Reredial exercise corrected deficiencies from September 5,19AR exercise. 10/30/85 FEMA again informed the Casmonwealth that 4A CFR 350 review was not progressing. Commonwealth provided RERP and local plans that were requested in 1985. 6/6/86 Comrenwealth responded to FEMA. The reply did not provide a schedule for completion.
- 9/E/96 FEMA informed MCDA of intent to conduct self-initiated review.
, Review to be based upon 198? RERP and 1985 Iccal plans. -
12/22/86 Comnonwealth forwarded copy of Barry Report. 8/4/87 FEMA Self-Initiated Review issued; six defici ncies identified. 9/29/87 FEMA stated that satisfactory correction of deficiencies would necessitate plan changes and some demonstrations. 12/9/87 Exercise exemption was granted to allow full participation exercise to be conducted by June 30, 1988. l l l 1 I l I
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POTENTIAL DEGRADATIO LOF CONTAINMENT SPRAY SY# TEM PROBLEM RUST FOUND IN THE PPIMARY CONTAINMENT SPRAY HEADER AND N0ZZLES AT PILGRIM l SIGNIFICANCE SPRAY PATTERN AND FLOW RATE MAY NOT BE THAT ASSUMED INTEGRITY OF HEADER MAY BE COMPROM! SED BACXGP0llND
* {
PILGRIM SHilTDOWN AND DEFUELED i SPRAY N0ZZLES BEING PLUGGED (6 0F 7 HOLES) CONTAINMENT SPRAY IS A REQUIRED SYSTEM AT PILGRIM OVAllTATIVE AIR TEST OF CONTAINMENT SPRAY SYSTEM AT PILGRIM IN 1982 GPRAY PIPING IN BWRs IS CARBON STEEL SPRAY PlPING IN PWRs IS STAINLESS STEEL CONCLUSIONS . OPERABILITY TEST FOR CONTAINMENT SPRAY SYSTEMS MAY NOT BE ADEQUAT FOLLOWUP LICENSEE TESTING N0ZZLES WITH RUST STAFF TO ASSESS NEED FOR SPRAY l I
. 0, T.ABLE 3.11-1 CPERATINO LIMIT MCFR VALL'Z3 McFR Operating Limit !
. l 7 g F8 8R t,0 1.41 , 1.44 0 to .1 1.42 1.45 i
.1 to .2 1.42 1.45
.2 to .3 -
1.43 1.46
.3 to .4 1.43 1.46
.4 as .3 1.44 1,47 ,
.5 to .6 1,44 1,47
. 6 to .7 . 1.45 1.48
. . 7 ** 8' .. 1.45 1.48
.8 ** +9 1.46 1.49 .'
.9 to 1 0 1.46 1.49
( l Amendment No. 34 70 2053-2
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ii FibuRE 3.11-4 ' E MAXIMUM AVFRAGF PL ANAR I INFAR HFAT GENERATION RATE - i s VERSUS
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- PLANAR AVERAGE EXPOSURE "
FUEL TYPE P8DRB265L ; O s D 1 12 I2) Ik.I I fCORE FLOW h 90% RATEO ! s
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2 FIGUHE 3.11 -5 MAXIMUM AVFRAGF PLANAR l INFAR HFAT GENERATION RATE - J VERSUS
- PLANAR AVERAGE EXPOSURE FUEL TYPE P8DRB282 o ~,-
T 12.0 32 1 CORE FLOWA 90% RATED cc*i
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iu m 10.4 i QO 10 9.8 s 9. s Sr: . 9 9, ' Ig 1 l l l 8 O 5,G00 IOpOO 15pOO 2q000 2p00 3pOO 40,000 3QOOO I: PLANAR AVERAGE EXPOSURE (MW @) . l
1 5 FIGURE 3.11-6 E MAXIMUM AVFRAGF PLANAR I INFAR HFAT GENERATION RATE ' ri
- VERSUS
'" PLANAR AVERAGE EXPOSURE FUEL TYPE P8DRB265H o '
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PLANAR AVERAGE EXPOSURE (MW @)
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' HAJ01 DESICM FEATURES !
5.1 SITE FIA'!VR11 . I Filgria Nuclear Power Station is located on the Vestern Shore of Cape Cod lay in the Town of Flymouth, Flymouth imacy Massachu-setts. The site is located at approximately 41'J1' morth latitude and 70835' west longitude on the Manomat Quin 931s, Massachusetts, Flymouth County 7.5 Minute serias (copographic) map issued by U.S. Geological Survey. UTH coordinates are 19-46446N-36921. The reactor (center line) is located approximately 1800 feet from the nearest property boundary. 1 5.2 tzACTot A. The core shall consist of not more than 540 fuel assemblies of 8x8 (63 fuel rods) and F8x81 (62 fuel rods).
- 3. The reactor core shall contain 145 cruciform-shaped control rods. The control material shall be boron carbide powder (34C) compacted co approximately 70% of theoretical density.
5.3 RIACTot VEs5E The reactor vessel shall be as described im Table 4.2.2 of the FSA1. N applicable design codes shall be as described in Table 4.2.1 of the FSAR. 5.4 CottrADeaDrt_ , A. The principal design parameters for the primary containment shall be as given in Table 5.2.1 of the FsAR. m applicable design codes shall be.as described in Section 12.2.2.8 of the FRA1.
- 3. The secondary containment shall be as described in Section 5.3.2 of the FSAR.
C. Fenetrations to the primary containment and piping passing through such penetrations shall be designed in accordance with standards set forth in section 5.2.3.4 of the FSAR. l l A"end ent No. 42 206m NY 1215!0
(. v 1 I Pilgrim Nuclear Power Station I Plant Familiarization Handout 1 Basic Floor-by-Floor Drawings of the Reactor and Turbine Buildings at Pilgrim Station. !
- These drawings are meant for training purposes ONLY. They are designed to give the student an insight of the major barriers and pieces of equipment on each level and their relative locations.
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N ( Paved Road N f^ u u A X x x i n n a x x ':. x x u x x n ; x x y x n ;; = x x x .n g x x x x ;- Re ay - F' Heyse N 3< A 6 y; Stairs b JC y ac 4 345 kV e+- d' Switchyard X
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Parking 1.ct u y BASIC OVERHEAD VIEW OF PILGRIM STATION
~ _ _ _
THf RE ARE 4 MasN STEAM LiceES ' IHf RE ARE 3 CONDENSATE PUMPS ^ "b IHf Rr ARF 7 CONDENSATE DEMINERALI7ERS Int RE ARE 5 FEECWATER PREHEATERS IN EACH SET (2 SETS) _ 1f f ELECTRICAL I Mk j*- GENERATOR j THE RE ARE 3 REACTOR IEED PUMPS __ _]
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l 1HFRE ARE 2 REACTOR FEEDWATER LINES s, p l YHLRE ARE 2 RECIRCULATION PUMPS p _ 3g TURBINE E s /
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mL m2 m, m2 l \ PRESSURE tow / rm v, 73 p. 3 TURBINES gj g, [ j vm Vm I vm %f %s Y r MAIN STEAM LINES CONDENSER CONDENSER l HF ACTOH i j N CONDENSATE PUMPS (3) i , r , r a a ^ T - FEEDWATER PREHEATERS FEEDWATER PREHEATERS REACTOR FEED PUMP CONDENSATE DEMINERALIZER N /" RECIRCULArON PUMPS Pictorial Representation of a Basic Boiling Water Reactor (BWR) Power Cycle i t,
l l l l l 1 NO1E: Wnen you are inside the turbine building or reactor building at Pilgrim Station, you will be able to find your way around much more effectively, if you can kjentify the ma'or components on each level, and can l m uss distinguish North from South at all times. Your task will become easier, if you simply remember that regardless of the floor / level you are on, the North l l wall will g be the wall which is facing the ocean, l 1 1
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AGENDA
~
!
- Problems-Solutions-Commitment i
1 l . Mgmt. Oversight & Self-Assessment e Overall Facility e Emergency Preparedness i 1 e Plant Operations e Security & Safeguards l e Radiological Controls e Refueling & OM . e Maintenance & Mods e Licensing. l e surveillance I
. Summary ,;
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i l FUNDAMENTAL PROBLEMS
~ > HAVE BEEN IDENTIFIED I
i e "Problem Ownership" is Not Understood I
- e Comprehensive Work Plan Does Not Exist 1
) . e "Work Plans" Are Not Widely Communicated I e PNPS Leadership Is Reactive l I i
.__.__-e..,.
I
~
l PROBLEM SOLUTIONS ARE SIMPLE - BUT NOT EASY l l
- Instituted Strict Accountability
! - Every Problem Has One Owner i
- &,r ers Are Accountable To Get Solutions i
- Develop Organizational Work Control Process
- Incorporates Long Term Plan
.I I - Define Process (By 7/3/86) l e PNPS Leaders Will Be Pro-Active I i i
d l 1 CORPORATE RESOURCES COMMITTED
! TO THE PNPS STATION MANAGER i
= Mbssage Personally Delivered By:
f i e Vice-President - Nuclear Operations I
' e Sr. Vice-President - Nuclear 1
l e Chief Executive Officer, BECO i i I i i j - 1 -_ - __ _ __ _ _ _ _ _ _ _ _ _ _ _ -
- e i
l J SIX WEEK ACTION PLAN l l ! ! ! ! ! ! 0 1 2 3 4 5 6 Hardware Schedule II Items - - ' i Work Control System ! Schedule III Items - Goals & Objectives f '
' Plan & Schedule l ~
SALP / INPO Action items I h Tect .i Strengthen Selective SALP / INPO Items i 1 1 l l
PNPS RECOGNIZES NEED FOR MANAGEMENT OVERSIGHT /SELF-ASSESSMENT
- Severi Day Self-Assessment
. Result of 5/19 Meeting Preparation
- Determined Some Fundamental Problems ,
e Six Week Plan
- Measure the Goals / Objective Program
- Develop Comprehensive Work Control Pian
- Develop Information Management System
- Complete Schedule ll! Tasks e in Addition
- Expand Management / Manager Training
- Establish Monthly Nuclear Self-Assessment Program Meeting
- Enhance Corrective Action Programs
4 OVERALL FACILITY l e Staffing - l - Authorized 39 Positions (22 in 4/86)
- Filled 10 Positi ens (Labor Action impacted}
I - Seek Additional Positions - 4
- e Attitude
- Compliance is Not Enough 1
- "Good Enough" is Not Good Enough l e Management Oversight -
1
- To Determine Root Cause in Management Systems j
- Self-Assessment
! - Establish Performance Evaluation Approach To identify i I Problems / Weaknesses. 1 i e Summary
- Changed Leadership f
- Company Resources Committed i
- Goal is Excellence l
~ OPERATIONS PERSONNEL MATTERS RECEIVING INCREASED ATTENTION i
e "Aggressive Hiring
- Hired Ops. Section Manager (5/86) il -Reassigned 2 Staff Engineers for Chie? Operations Engineer -(6/86) i
'l I
- Hired Chief Chemical Engineer (4/86)
~
- Hired 3 Shift Technical Advisors (2/86) l
- Hired 10 Nuclear Plant Operators (2/86) (33% increase) l l
- Long Term Staffing Analysis / Plan in Progress (12/86)
- Apprenticeship Program (Pending Union Contract) l L
- e. Restructured Shift Schedule / Reemphasized i
Accountability for Ove~rtime Control (3/86) l e Four Nuclear Plant Operators Passed Licensed i ' Exam (5/86) I' l - Increases Staff From 8 to 12 RO's I i
~
- l . .
i 4 il BECO CORRECTING ! RADIOLOGICAL CONTROL WEAKNESSES i i . e Management Oversight Enhancements
- Designated Radiological Project Liaisons (3/86) i 1
i and lead Technicians (4/86)
- Strengthened Radiological Occurrence Report Program (5/86)
RadiologicalInformation Managemerit System Operational (5/86) 1 - i !
- Staffing '
- Chief Radiological Engineer (Offer extended 5/86)
) 1 - Added Second ALARA Engineer (4/86) q Hired Rec' Materials inventory Supervisor (5/86) , L j - Authostzed Eight(8)' Technicians (5/86) (35% increase) ,i (Labor Action impacted) i e Group Addition7/86)(Of Corporate Radiological Engineering ,
- Staffed With 3 Senior R7diological Engineers f - Provides independent Oversight And Support l
BECO IMPROVING MAINTENANCE AND i : l MODIFICATIONS ACTIVITIES i ORGANIZATIONAL IMPROVEMENTS
- Established Maintenance Planning Function Created Centralized Site Procurement Support e Refocused First-Line Supervisors Toward Field Activities MATERIAL CONDITION INITIATIVES Backlog MR Reduction i
e
- Fire Protection Project Manager
- Housekeeping ' Area Owners" TRAINING
~
! * ' Formal Labs / Classroom Training i
- INPO..Self-Evaluation l
.l j
- Apprenticeship Program i _ _ _ _ _ _ _ _ _ _ ..
1 I i INDEPENDENT TECHNICAL REVIEW OF SURVEILLANCE PROGRAMS l ~ PHASEI
- Protective instrumentation Review l
- ECCS Simulated Automatic initiation i
e Results: HPCI Testing and RCIC Relays
- Procedures Revised Thru inter-Departmental Review i
I PHASE ll -
- Complete Remaining Surveillance Requirements Target (6/86)
~
- Revise implementing Procedures i PROGRAM IMPROVEMENTS j
- Improved Response to Abnormal Results i
- Independent Verification incorporated into Surveillance Procedures
- Incorporate Comments from Independent l
Technical Review i
BECO UPGRADING EMERGENCY
~
l RESPONSE-CAPABILITY l
! e New EOF Functional (6/86)
- - State Of The Art Protected Facility (PF-5)
- Improved Communications and Layout
- Reorganization of Emergency Reponse Team l e Emergency Preparedness Staff increased l - Hired Assistant Coordinator (3/86)
. - Authorized 3 Additional Positions (5/86) j Expected On-Board (9/86) ,
i i e increased Emphasis on Drills / Exercises
- Tested New Critique Form (4/86)
! - Performed Successful Re-Entry /HP Drill (4/86) i - Reviewing Tested Scenarios From Other Utilities ! - Increasing Frequency of Drills l i
~
COMPREHENSIVE ACTIONS TO
~
UPGRADE SECURITY l
. Augmenting Security improvement Program j (Previously Submitted to NRC)
- - including Clarification of Security Objectives-Plan (6/86)
- Scheduling Equipment Repairs
-- Integrating Security Corrective Action Program with NUORG i
I
- e increased Staffing 4
- BECO Supervisors - Hired 4 of 5 (6/86) l - Corporate Nuclear Security Specialist Hired (4/86)
I - 20 Additional Security Officers in Training 1 i i l 1 l ) } i - .
1 !' i a l l
~
CONTINUED EXCELLENCE IN . ! REFUELING / OUTAGE MANAGEMENT i h .
! i l
- Instituted ' System Window" Concept For RFO-7 :
l ' 1 e Monitoring Paperwork Closeout as a Scheduled Activity l' e Reviewing Recommendations / Good Practices ! - New I&E Module j - Other Plants f f i l
- l 1
f i
I TO CONTINUE THE STRONG , LICENSING PROGRAM [ . !
- Assessed Tech Specs for improvement Areas
- Streamlined Review Process
)
- Prioritized Pending Changes
- Enhanced Tech Spec Change ControIProcess l
- Developed Policy on Tech Spec interpretation l
j . 1 5 i I I I I
l CHANGES TO QA PROGRAM
- Improve Timely Corrective Action for DR's
- Revised BEOAM
- Daily Meetings With NOM l
- Extension of a' OA Program to Balance of Plant j
- Incorporate INPO Good Practices
- Developed Training Module on Corrective Action 1
I
- Corrective Action Program Being Revised .o incorporate Provisions for identification and i
l Designation of Non-Regulatory Problems at PNPS , i l I
~
} i INCREASED FIRE PROTECTION - 1 DECREASED FIRE WATCHES ) e Organization / Staffing l 1 - Assigned Fire Protection Project Manager (3/86)
- Re-Assigned Fire Protection Engineer To Operations (1/86)
] I - Improved Oversight e Program issues f - Revised Equipment Spec (Allows Catalog Purchase) (3/86) 1
- Issuing Fire Watch Trending / Weekly Reports f,
l 1
- Current Results i
! - Fire Watches Reduced By 70 % I 1 l l 1 I ) \
e L ) SIX WEEK ACTION PLAN ) I I I I 4 I I I 4 i i I 4 I I 5 6 2 3 4 0 1 ) Hardware
; Schedule II Items - i i
l Work Control System Schedule III Items - i i Goals & Objectives ,
' Plan & Schedule SALP / INPO Action items i
Test I i l Strengthen Selective SALP / INPO ltems I I I i 1
.-. - _ - _ - - - - - . . - _ _ = _ _ _ _ . . - _ _ - _ - - --
I I i i i i
SUMMARY
i i f
- Changing Management Attitudes l
) i I
- Strong Direction .
1 !
- Continuing Support l
l i I
}
i
i
..~. . \
IMPROVEMENT INHIBITORS l i j
- Incomplete Staffing l
(Operators, Key Middle Management) o Prevailing Attitude I (Improvements Already Made Have Fixed The Prob!em) i e Reluctance To Acknowledge Id ntified Problems 1 o Lack Of A Program To f identify Weaknesses ) 4 l I i l l I - - ---- -- - - - - - . -
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