ML20205E795
| ML20205E795 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek, Three Mile Island, 05000000 |
| Issue date: | 02/01/1985 |
| From: | Naylor W, Ross D GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20205E603 | List: |
| References | |
| FOIA-86-293 PROC-850201, NUDOCS 8608180487 | |
| Download: ML20205E795 (267) | |
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SAFETY REVIEW TRAINING PROGRAM DESCRIPTION Submitted: W. R. Naylor Sat %ty Review Training Coordinator 1 Concurred: J N U J.[R.' Thorpe,Dipector,LicensingandRegulatoryAffairs Concurred * % R. N. 4thitesel, Nu' clear Safety Assessment Director l
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Approved: ' d bMb D. Ar Ross, Manager of Corporate Training ! February 1,1985 i I l l J1705 l 8608180487 860807 PDR FOIA WEISS 96-293 PDR
1.0 GENERAL i 1.1 Purpose . l 3 The purpose of the Safety Review Training Program is to familiar-ize prospective Safety Reviewers with the GPUN Nuclear Safety Re-view and Approval Program Policy and Procedures and to discuss specific topics identified in Reference 1.3.10. It provides sup-plemental information to individuals whose technical expertise otherwise qualifies them for certification as Responsible Techni-cal Reviewers (RTR) or Independent Safety Reviewers (ISR), or both. Note: This training does not apply to TMI Unit 2. 1.2 Scope The Training Program is designed to provide a common perspective to those individuals involved in the Technical Review or Indepen-dent Safety Review of items which have potential safety signi-ficance or otherwise require safety review by Technical Specifica-tions or other corporate requirements. 1.3 References 1.3.1 ANSI /ANS 3.1 - 1978 Sections 4.7, 4.4, and 4.6 1.3.2 10 CFR 50, Appendix B (II) 1.3.3 Regulatory Guide 1.8 - Personnel Selection and Training 1.3.4 TMI-1 Technical Specification Section 6 1.3.5 Oyster Creek Technical Specification Section 6 1.3.6 CPUN Policy 1000-POL-1291.01 "GPU Nuclear Safety Review and Approval Policy and Procedure." 1.3.7 GPUN Procedure 1000-ADM-1291.01 "GPU Nuclear Safety Review and Approval Procedure." 1.3.8 Oyster Creek FSAR 1.3.9 TMI Unit 1 FSAR
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t3 o k (c L.3.10 Met-Ed/GPU letter LIL 347 dated December 8.1981 regarding { p.y,< . tn /[i. reviewer training. 2.0 RESPONSIBILITIES Due to the large number of people required to receive safety review . process training and their diverse backgrounds, responsibility for the content and conduct of training is shared. The coordination, schedul-ing and conduct of the generic training, which is required for reviewer JL705 .-. -- . - _ _ _ _ _ _ __ _ ._. _ _ . _ . ._ _- _ _- _ _
l certification, will be the responsibility of Corporate Training. The l responsibility for all aspects of any Division Specific Training rests l
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l within each division. A more detailed outline of responsibilities fol-Lows. - 2.1 Manager - Corporate Training is responsible for the overall con-duct of the training program including: 2.1.1 Aid in the development of training program objectives and content. j 2.1.2 Approve the Training Program Description. 2.1.3 Assist, as required, in the selection and assignment of subject area specialists to serve as instructors. 2.1.4 Determine the requirements for evaluation of the program instructors and students (e.g. classroom interaction or written examinations). 2.1.5 Coordinate the scheduling of generic training sessions at all locations. 2.1.6 Provide assistance to generic and division specific instructors in the preparation of lesson materials. 2.1.7 Maintain documentation of generic training attendance and provide copies of attendance sheets to division safety review coordinators. o/-
/ hf-h 2.1.8 Maintain safety review training lesson plans. # ( '
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0b Administer and document examinations / quizzes or other d' g<2.1.9 methods of evaluation. 6)(AM.Q)R6VA.I'dj'
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go - i '* 2.1.10 Annually review lesson / program materials. 2.2 Nuclear Safety Assessment Director is responsible for: M'2.2. Providing qualified instructor (s) for training assigned - ,, Y kc 'f,3 gff herein to NSAD. % '-l 6 q /-/ .f r-J f W $p^ I' Y
/J 't b.# I WV' Providing C associated idssolHCX h 5 materials. W Y'E' hv4 N 2.2.2 n plans arid handout *
[j' 2.2.3 Assisting Corporate Training in scheduling and coordina-ting generic training sessions. 2.3 Director, Licensing and Regulatory Affairs is responsible for: 2.3.l f roviding P qualified instructor (s) for training assigned
, p / erein h to Tech Functions - Licensing.
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Ih 2.3.2 Providing associated lesson plans and handout materials. 2.3.3 Assisting Corporate Training in scheduling and coordin- e 7 4 ating generic training sessions. -p 8 *
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- 2.4 Division Directors are responsible for:
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.- 2.4.1 Establishing division requirements for optional di ion '
specific traintn_g. JY e t lJ C aSJt1f h g yg yqf aidJ: di W 5 IN j, i% f% r t.:7 up
*. 2.4.2 Development, impi mentation, and pres tation of' e..a .g,+.
f'g.) . 5-y ', ofjp appropriate division specific training modules, when g,,
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2.4.3 Selecting subject area specialists to serve as instructors. (-2.4.4 Evaluating the content, conduct, and effectiveness of division specific safety review training. 2.5 Division Safety Review Coordinators are responsible for: 2.5.1 Coordinating division requirements with the Corporate Training Department for generic training. 2.5.2 The conduct of safety review process training activities as needed for division specific training. 2.5.3 Maintaining documentation of generic training attendance and, if needed, documentation of division specific train-ing attendance for all RTRs/ISRs in their division. 3.0 REQUIREMENTS r 3.1 The generic portion of the Safety Review Training program shall be approved by the Manager, Corporate Training in coordination with the Nuclear Safety Assessment Director. Approval may be provided
*hrough issuance of a program description or by memorandum with program outline, list of instructors, and schedule information.
4.0 PROGRMi 4.1 Objectives Following the successful completion of training, participants should be able to: 4.1.1 Define their safety review responsibilities and duties as an RTR or ISR. 4.1.2 Define the role and responsibilities of the Preparer. a .5 h t- W e b b // k:t cuqAtJ 6 I' st70s [O-( ~.It W. I 5 (csujJ bu (; lh Q hv5 hoA (WJ h W T ,% - W&$ ~)~Lt QWJA2Ao OQ p yf (?U h-) - S D 5 :1 D r.! x i n>r - ( s a r_. F , . . . ci 7/Jy .(. OFLy #U M '"
4.1.3 Summarize corporate policy and procedures regarding the safety review process. 4.1.44 Describe the guidelines for performing a safety review. 4.1.5 Identify licensing documents and processes applicable to the safety review process. 4.1.6 Demonstrate a basic understanding of the structure and general content of the Technical Specifications and the FSARs. 4.1.7 Describe in general terms the concept of a " safe operating envelope." (?,( j r3 l h d'.h lY C-4.2 Training Outline -
# # B oth the initial and refresher Safety Review Training Program con-sists of a required generic segment and a suggested division specific segment. Parts of the generic training may use TMI-1 and/or Oyster Creek documents as points of discussion. Either presentation fully satisfies the objectives of this training program as outlined in Section 4.1, and fully satisfies the training requirements of Reference 1.3.7. Therefore, formal
" cross plant" training is not required. In all cases, it is the responsibility of the people assigning RTRs and ISRs to ensure that those assigned possess adequate detailed administrative and technical knowledge, or are properly indoctrinated and supervised, prior to performing their assigned review tasks.
The following outlines of initial and refresher training programs are illustrative and may be modified to suit the needs of the stu-dents. They can also be adapted to other variables such as class size, background, previous training, etc. 4.2.1 Generic Training (Initial) Formal training covering the major features of the GPUN Safety Review and Approval program, policy and procedure i is required prior to certification as a Responsible i Technient Reviewer (RTR) or an Independent Safety Reviewer 1 (ISR). Also required is an overview of the licensing process and documents, and the Principles of Safety, as outlined below. This overview is intended only to l reinforce the important relationships of these subjects to i safety and safety reviews and not to provide detailed I , technical instruction on specific topics in these areas. I 4.2.1.1 Safety Review Process (Prepared and presented by NSAD) A. Discuss the origin of the process ; 1 1 1 i 1 J1705 l
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- 1. P. R. Clark - Origin of the Process; Testi-many of DfI-1 Restart Hearings (1981) Sum-marize 4 major elements of licensee's safety
- review program. Note this is again reflected in Corporate policy.
- 2. GPUN Safety Review and Approval Policy as stated in Section 4.0 of Pol. 1291.01. Re-view process required to ensure that plant changes / mods and procedure changes do not result in violations of the criteria for which the plant was designed.
' 3. GPUN Safety Review and Approval Procedure (Adm. 1291.01)
B. \ Summarise the Review and Approval Matrices. aIdentify the major subject areas. (Depending h
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(,, y upon the responsibility of the student's division).
\ G , , g Q.U C. Review the major parts of 1000-ADM-1291.01, in-p p cluding exhibits.
D. h# , Responsibilities. Review responsibilities per
/y }h corporate procedure and tech specs of:
hA[ f k(13\gMQ1. 2. Preparer
/
I Responsible Technical Reviewer g,k' /d V'gIg ' 4.3. Independent Safety Reviewer Independent On-Site Safety Review Groups y/ - (IOSRG)
- 5. Concurring Parties i A (, d 6. Implementation Approver 10, jh #
- E. Procedure Changes. Emphasize that Safety Review procedures may be changed. Encoursge partici-g)$p pants to provide feedback to procedure " owners"
\J- regarding problems with procedures and suggest-ions for improvement.
F. Resolution of disagreements regarding nuclear safety concerns, including the role of the Ombudsman. J1705 .__. __ _ _ _____ ___ - _ _ - . _ _ .- .-_. _ _ _ _ _ __ _ _.
4.2.1.2 Principles of Safety: (Prepared and presented by Tech . Functions. Licensing) 4 Overall Coal: " Protect the health and safety of the public" A. Approach:
- 1) NRC defines requirements;
- 2) Licensee commits to them in FSAR;
- 3) Licensee responsible for assuring requirements are met; and,
- 4) public is protected. -
- 5. Where do the requirements come from?
,1) GDC
- 2) Reg Guides
- 3) Standard Review Plans
- 4) Branch Technical Positions
- 5) Specific plant requirements from licensing of plant (NRC staff, hearings)
C. What are some of these requirements?
- 1) Single failure criterion (redundancy)
- 2) Physical & electrical separation &
independence
- 3) Natural phenomenon - earthquake, wind, flood
- 4) Fire
- 5) Off-site /on-site power failures D. How are they used to design plants?
- 1) Define events that plant must be designed against (e.g. LOCA, steam line break, fire, plane crash).
- 2) Appropriate combination of requirements and events.
- 3) FSAR describes these events and assumptions as well as the acceptance criteria for the events.
- 4) All of these events define the desian bases for the plant.
- 5) Historically, large LOCA has been the most i
limiting event and it is the design basis accident (DBA). Design and operation of the plant within the limits specified in FSAR and Tech Specs provides a " safe . operating envelope" that assures the public health and l safety is protected. 1 l l J1705 l l
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4.2.1.3 Licensing Documents and Process: (Prepared and presented by Tech. Functions, Licensing)
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A. Provide an overview of the licensing process from construction permit to operation to help tie licensing documents together, including subse-
,quent change mechanisms.
- 1) Discussion of the use and content of the FSAR.
- 2) Design Basis Accidents / Transients -
Discussion of Chapter 14 FSAR accidents and ATOG.
- 3) Discussion of the use and content of the Technical Specifications.
- 4) Non Routine Reporting Requirements -
Discussion of 10 CFR50.73 and 10 CFR21 reporting requirements. 4.2.1.4 Additional Related Topics - The training program's content may be supplemented by additional presenta-tions or through the use of additional written hand-outs prepared by cognizant departments within CPUN. . The Corporate Training Department shall request this additional training support whenever they determine 7'g j d the need exists. gL , 4.2.2 Division Specific Training (Initial)
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,FormaldivisionspecifictrainingneednotbemandatoryU{
g/ for certification of RTRs and ISRs, depending on the I(( policy established by the responsible _ Division Director. cl 95 When directed by the responsible Division Directors, the
\1 Division Safety Review Coordinators or designated alter-nate shall determine the specific training needs by con-sidering factors such as the number of people involved, their prior experience with the safety review process and the "on-the-job" supervision available. Paragraph 4.2.2.1 is a typical outline for division specific training.
4.2.2.1 Division Implementation (Prepared and presented by the l Responsible Division) l l A. Describe division level procedure (s) that relate ; I to the implementation of the Safety Review l Process and discuss mechanics of implementation , i in the division. 1 l J1705 ! l
9 B. Discuss past experiences with the process - emphasize areas and methods that are most suc-cessfbl - discuss actual and potential problem 4 areas and how to avoid or mitigate. C. Provide additional emphasis on the duties and responsibilities of Preparers, RTRs, and ISRs. D. Provide examples of good and bad safety reviews and discuss the qualities that contribute to their categorization. These should be related to familiar division paperwork and activities. If ) possible, review real life examples of good or 1 bad safety reviews. 4.2.3 Refresher Training Refresher training shall be accomplished through the g 0 periodic presentation of selected topics as directed by the Manager Corporate Training. It is intended that this
. I h Ij kyc8 refresher training consist of an update on the review
\6M g ( [ ri process. Sections 4.2.3.1 and 4.2.3.2 illustrate an f ,y outline for the required generic refresher training.
pj U" Section 4.2.3.3 is a suggested division specific training outline. yU f 4.2.3.1 Review Safety Review Process (Prepared and presented by NSAD) A. Evaluation of the process. B. Changes in the 1000-ADM-1291.01 procedure. C. Changes in the Review and Approval Matrices. 4.2.3.2 Review Recent Changes in Licensing Basis Docu-ments for TMI-1 and/or Oyster Creek (Prepared and presented by Tech Functions - Licensing) A. FSAR changes (including Design, Basis Accidents / Transients)
- 5. Technical Specification changes.
C. Other Licensing Basis Documents Changes D. Non Routine Reporting Requirement Changes (10 CFR21,10 CFR50.73 etc. ) 4.2.3.3 Review of Division Specifics (Prepared and
. presented by responsible division)
A. Division implementing procedures changes B. Mechanics of implementation (Safety Evalua-tion processing and storage. Reviewer lists, etc) l C. Recent examples of actual safety reviews. l J1705 l l
4.2.3.4 Susumery of the effectiveness of the process (Prepared and presented by the division involved with input from NSAD if required) A. Aspects of where and how it is working well.
- 8. Areas of difficulty.
C. Areas needing improvement. 4.3 Program Scheduling A program of periodic initial and refresher training presentations will be established by the Corporate Training Department. l l t l l i j J1705 : l
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p - . Page 3 of 3 SCHEDULE NOTES , (a) TMI-I Plant Engineering - includes Special Nuclear Material. (b) TMI-I Project Engineering - includes Startup & Test and Technical Functions. > (c) Corrective Action Program - includes MNCRs, QDRs, LERs, etc. (d) Radwaste Management Program /Hittman Nuclear Corp. - includes Radwaste Shipping and Process Control Program. (e) Special Processes / Programs - includes Welding, NDE, Heat Treatment. (f) Bechtel led (internal and external) audits with GPUN TMI audit participation (tentative time frames). (g) Audit of Power Authority of New York - CMAP team member (provided reciprocal man-hours are supplid by Corporate Audits to site). (h) FASS - Functional Audit of Safety Systems (Turkey Point). (1) AIARA Assessment performed for Radiological Controls satisfying NRC commitment. CENERAL NOTES Note 1: If a Bechtel auditor is on the TMI audit team, involvement is for THI-2 only. 00950
4
.. t . . e e, c gg 7 Post Office Sox 480 Route 441 South Middletown. Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:
717 948-8572 March 24, 1986 6113-86-024 Mr. Charles Stauffer Plant Manager Air Products & Chemicals, Inc. 2710 Broadway Camden, New Jersey 08104 k
Dear Mr. Stauffer:
As we discussed on Monday, March 24 I am requesting your confirmation to additonal requirements relative to bulk compressed air which may have been supplied to GPU ) Nuclear's TMI-1 facility on GPUN purchase order numbers 019430 and 035330 to Air . Products & Chemicals, Inc. It is our understanding that any compressed air supplied under the above referenced purchase orders would meet the following additional requirements:
- 1. Gas would only be manufactured and shipped from API's Camden, New Jersey facility at 2710 Broadway.
- 2. Cas would be manufactured and supplied utilizing the same procedures which ,
would be invoked on same gas procured Important To Safety.
- 3. Dewpoint of gas is equal to or less than -400F at 100 ps1.
- 4. Gas would be filtered to a minimum of .9 micron.
I would request the person responsible for your Quality Assurance function to please confirm the accuracy of this information and respond to the undersigned. i I appreciate your cooperation in this matter. If you require any further information, please contact me at (717) 948-8000 Extension 8572. Sincerely yours,
? i. >
Ralph F. Munz QA Engineer, TMI-1 dlw c QAE FileC M CARIRS l GPU Nuclear Corporation is a subsidlary of the General public Utilities Corporation N
O . M . na w,inem. yy 1, ^!]: IGD Lenign District g - (315)481-7725
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h @p Purchasing Dept. p , SUE BROCK ' I GPU NUCLEAR CORPORATION P.O. B0x 480 - MIDDLETOWN, PA 17057 L i THE GAS SUPPLIED AGAINST PURCHASE ORDERS ( 3. NUPSERED 019430'AND 034330 MANUFACTURED i AT CN CEN, NEW JERSEY IS IN ACCORDANCE WITH THE SAME PROCEDURE INVOKED ON l l ITS SYSTEMS, AND THIS GAS IS EQUAL TO OR l' BETTER THAN -40' FAHRENHEIT DEWPOINT AT 100 PSI FILTERED TO .09 MICRON. l' li.. LLIAMS l DISTRICT MANAGER LEHIGH DISTRICT rs A RI.N:KLS f' c"*fuC 1@ L .
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REQUISITIONER ..: __ - FY.d*,t"* M-Dg PAGE 2 PUR - 3 ORDER CPU NUCL[EA.."CORPO2ATION REOs 3210-86-0873-000 ;=lf.JWJim s avocas. t ,4 TP-035330 I PHILADELPHIA TERMINAL: (609) 365-4500 [ IN PA: (800) 322-9092 l
- z. l 1 3 0 0 , 0'0 0 01027673'IN' #dNY COMPRESSED AIR, IN BULK 1.500 l CF 4e Z'S 4 JIIfRN11LfRIAL GRADE WITH A DEWPOINT PEll C CF l >
LESS THAN OR EQUAL TO -10 DEG. C AT l' 100 PSIG - j I~ J!OTE: lI ROXIMATE
)., . .y. t&\ueb t f-a m,
{IT a-n e i v. I
? 1 00173534-0 TUBE TRAILER RENTAL 6,5i10.000 l EA PER EA j i
$500.00 PER MONTil. l I
A. TIIERE WII.L BE NO EXTRA CHARGE FOR WEEVENDS, !!OLIDAYS OR E!1EltGENCY l Dl; LIVERIES. . l H. DELIVERY TICKETS TO BE DELIVERED TO WAltEllOUSE fl Tile SAME DAY AS l DELIVERY IS tlADE. ALL DELIVERIES TO TMI WILL BE MADE REGARDLESS OF WORK STOPPAGE OR ! C. DISPUTE BETWEEN VENDOR AND UNION. l I D. AIR PRODUCTS WILL BE REQUIRED TO FOLI.OW NORMAL OPERATIVE PROCEDURES, l RULES, RESTRICTIONS AND REGULATIONS CONCERNING SHIPtiENTS TO THI. l l E. PRICES FIRit FOR CONTRACT PERIOD; REFERENCE GFUM OUOTAT7.Ori !
$NB00500230 DATED 1/29/86. l THIS BPO SUPERSEDES PURCilASE ORDER #0!9430.
ACCOUNTS PAYA9LE: INVOICES FOR TRATI.ER RE!ITAT. Gif ALL HE 'IMl!F'S'4TFD TO i
!!. ROSS FOR i.03A APPROVAL.
AIR PRODUCTS WI LL GIVR 50 PSIG RESIDilA L Cill'.DIT ON "T'!'"I 'I'I' U ' i n' s. l
1 REQUISITIONER - I p
/ PURC ORDER M .5 % %
JJ PAGE 3 CPU NUCLEAi(CORPORATION REOs 3210-86-0873-000 MSE!WJ. tp 9y;i:-
"IN THE EVEtIT FUNDING UNDER THIS CONTRACT HAS NOT I4EEN EXPEtIDED BY THR PERIOD OF PERFORMANCE EXPIRATION DATE, HEMAINING FUNDS MAY BE UTILI:'J:D FOR CONTINUATION OF IDENTICAL SERVICES UP TO AN ADDITIO iAL SIXTY DAY PERIOD. IN NO EVEIIT, liOWEVER, WILL GPUNC RE LI AllLE FOR SEltVICFS RENDEITEI) DEYOND T!!E AUTilORIZED FUNDING DOf,LAR LIMITATIO;l USTABT,ISiiED OR SilE:EXTENDSli TsRIOD OF PERFORMANCE, WHICIIEVER OCCURS FIRST."
INVOICES SIIALL DE SUBMITTED BY THE VENDOR FOR EACll INDIVIDUAL SilfPrtrt1T. l-h INVONES'shdLLBEkIdhphkhlhhAIDBYACCOUNTSPAYABLEUPONPRCOPOl'
- DELIVihtY AllD ACCEPTANCH OF SAME.
THE PEOCURE?!ENT DEPARTMSNT RESERVES TIIE RIGilT TO CllANGE hi1D/OR C7sNUEL
- ANY FORTION OR ALL OF THIS PilRCHASE ORDUR, WITil NO OBbtGATION Ol'.
j MONETARY COM1ITMl:NTS OTilER THAN FOR MATERIAL OR SI:ltVIC8 HSC!JtVED POIOR
, g TO CilANGS OR CANCELLATION.
+
- e
'I!4 VOICES SilALL HE ISSUED TO:
l GPU NUCLEAR CORPORATION PO BOX 1010
- READING, PA 19603
- ATTN
- ACCOUNTS PAYABLE DEPARTHENT INVOICES AND PACKING SLIPS MUST SHOW Tile BLANKET PURCIIAni: OltDH*t NU.tPER AS WELL AS COMPLETE DESCRIPTION OF 11ATERIAL DELIVERED. PACKIllG St.TPS MUST DE PRESENTED TO WAREllOUSE il FOR HECEIVING PURPOSES.
i i I l f I i
.? , REQUISITIONER J d f- g gg v PAGE 4 PURC h OROER CPU NUCLEAn' CORPORATION REQ: 3210-86-0873-000 _ __" ..{!!T 7
..ca .
,,o" %
eevoius.
. Tn o v, t .a c IMPORTANT NOTICE
- 1. Ol! DER NO., F.O.B. POINT AND PRICE TO APPEAR ON ALL INVOICES, t 2. TRUCK DELIVERIES WILL NOT BE ACCEPTED AFTER 3:30 P.M. OR ON COMPANY DU31GilATED I!OI,ItihY".
UllLESS OTHERl11SP, SPECIFIED.
.l . ALL CONDITIONS APPEARING ON THE REVERSE SIDE ARE A PART OF TIIIS 06 DER.
- 4. ALL PACKAGES SIIIPPED AGAINST Tills ORDER MUST REFLECT PART NAtill, P3itT t:UMI3ER, A N D P .t.'. NO W ' 'l' .
- 5. THE VEi3 DOR SHALL ASSURE TIIAT TIIE MATERIAL IS PACKAGED TO PREVP.NT DA*4 AGE I)URIliG SillPPIrlG, RECEIVING AND LONG TE14M STORAGP..
- 6. ALL QUALITY ASSURANCE DOCUMENTATION . SHIPPED AS PART OF Tills ORDER WILL BE 1.PGT.Di.M.
- 7. ACI~NOSILEDGEMENT FOR ' EXCEPTIO!IS .ON,LY, AND,f0RWAP.D TO:
GPU NUCLEAR ColtPORATION
! PO,* DOX 4 80, ROUTE 441 SOUTII MIDDLETOWN, PA 17057 I *
'ATfN: TM1 PURCHASING
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i I TOTAL Fill 4 DING LEVEL. 440T TO EXCE1 D 1 1,0 6 J . 1 l 1
- stilr;:,T ACTI VITY 113:?01 h0/bu 95-3210-G3013 ItEF '.R e.L.:, lif f.' I !*Il " i t.: ;Mr:na. :,, .it' ppi . p . s ; 7.. .. ;> ,
\
PA. SEl.HCTIVE SA!.ES AIID 11SE TAX OIRECT PAYMCNT PE:RMIT NUI!PCP OU l4f! \
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SYSTD1 DESCRIPTION - by I. R. Reed t ' INSTRUMINT AND CO:! TROL AIR SYSTE4
, LTTROPOLITAN EDISOU COMPANY THREE MILE ISLAND UNIT 1
. e Issue Date October 28, 1969
. ~
I s l l Preprtred by:
. Gilbert Associ*tes, Inc.
Reading, Pe:.ncylvenia I i
~........__.... _ _ . . . _ _ _ .... .,,, ,....,i r.s.es. . . . . - . . - - . . . - . . . - . - - - - - - - - -
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. 6 ___- , . _ _ _ _ _ _ _ _ _. . ____ ._
j system thrcuch cn cil rIn.. oval filtsr to th2 instrumInt air systcm if the instrument air pressure continues to drop below the set pressure
' which initiates starting the standby instrument air compressor. ,
An automatic, heat reactivated air dryer in combination with a pre-filter and'an afterfilter removes dirt particles and moisture from
~
the air prior to distribution. The dryer requires both electrical power and pneumatic power for' operation; electric power is supplied from the station bus and pneumatic power from the air compressor. The loss of either vould result in the loss of the capability of the dryer to reactivate the dessicant and ultim'ately to dry the air. The passage of air through the dryer or through the dryer bypass is essential to plant operation; therefore, in order to reduce the possi-bility that the dryer does not become the one item whose failure could caus,e the loss of air, the dryer is furnished wit,h a special h-vay switch-over valve which eliminates the possibility of air shutoff
' ~
during a switchover failure. The schematie di,agram for the system is the instrument and station service air flow diagram, Drawing C-302-271. For a description of the instrumen't air cooling system, refer to the Secondary Service Closed Cooling System Description. 1.3 SYSTD4 DESIGH RLQUIPJME!TS The instrument ar.d control air system is designed to centinuously g deliver clean, dry air at 100 psis, in sufficient quantif,les to use - points throughout the plant. AlthouEh the sy.ite: is nc*. t quired by the Fr.tincerca Ec.fe._,uards Syc:c..s i it has been desicr.ed with a high. degree of inteCrity: I
, _, . - - , . - . -n - - - - - - - ,
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- a. Redundancy of co:npressors, aftercoolers, and receivers is, provided for with additionai backup from the ho,use service air system.
- b. The instrument air compressors, afterco'olers, receivers, and air dryer are located in the tornado and aircraft protected intermediate building.
- c. Instru=ent air cocpressors, aftercoolers, receivers, and dryer are designed to structurally withstand setanic conditions.
- d. The capability is provided to manually load the instrument air compressor to diesel, generator output from the control room. ,
e.- The air piping in the auxiliary building is Seismic Class I.
- f. . Non-seismic piping outside the auxiliary building is arranged to be isolated from the balance of the system in the event of loss of integrity. This is accomplished when the isolation control valve closes on lov downstrean pressure; it is necessar-/
to " defeat" this contr'o1 valve whe'n initially pressurizing the system., . g.' All pressure vessels are designed in accordance with the ASME Codes for Unfired Pressure Vessels. The backup house service air compressors feed into the instrument . air distribution systen via an oil filter and then thru the air dryer. ~
'The instru=ent and centrol air system was purchased with the follow- ,
ing general air require =ents:
- a. Flov Rate - 25T cfm free air at 300 ft above sea level (using 60-hp ectors without utilizinc overload factor).
t
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- b. Normal di: charge pressure - 100 psig. .
/p c. Intake pressure - 300 ft above sea level. .
. d. Intake air te=;erature 90 F.
- e. Maximum allovable oil addeb to intake air - none.
- f. Air temperature leaving aftercooler - 105 F mar.imum.
Mol'sture content of air 1 caving dryer - minus ho*F dev point 6 h . at 100 psig. . .
- h. Maximum particle size of air leaving afterfilter - C.9 microns.
. The following service are available to the system: P
- a. Cooling vater vith te=peratures from 60 F to a maxi =um of 95 F; JP
- e go L normal pressure is 80 psig.
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[ ~b. 480-volt a-c 3-phase , 60-h: electrical power. A
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3- _ OQA Manager Dato: 3/21/86 rROM: To: Pf. J. Ross, Operations Director, TMI-1 QDR-OLL-030-86 File No.: 030-86
Subject:
QDR No.: The attached QDR has been evaluated by OQA and found potentially reportable.
] Please review the QDR and take action you consider necessary to inform Regulatory Agencies, Upper Management and GRC/PORC Committee Chairmen. You are requested to furnish written acknowledgement of the receipt of this notification. Please provide copy of completed evaluation report to OQA Manager for place mt in QDR file.
The attached QDR is forwarded for corrective action. Please arrange for the l
] completion of Section 3 of the (DR, and provide a date by which corrective action j j
will be completed. Return the QDR, with Section 3 completed, to the OQA Manager. j You are requested to furnish written acknowledgement of the receipt of this transmittal. i For your information. I The attached QDR and supporting documents are forwarded for your retention as QA , Records and are to be retained for the life of Unit I/II. You are requested to : furnish written acknowledgement of the receipt of this transmittal, j l Examination of our records indicates that this QDR corrective action is overdue. Please provide a revised completion date and interim status report to the OQA l Manager for approval. y Other/ Additional: Please send your response for the attached 00R to J. Souder. 00h Trir. 257 by April 21,1986. ( A blank response page is attached for your use. ) i Also, please sign and return this transmittal form upon receiot. Thank you. CC: ( ) Chairman FORC ( ) Chairman GRC ( ) Director QA D6 Mgr. NSAD ( ) QA Design and Procurement Manager (Site Supvr) ( ) Operations QA F.anager ( ) QA Manufacturing Assurance Manager ( ) Site QA Audit Surv. (X Manager OA Modifications /Cperations (M Unit Manager I/II ( ) Dir. Matl. Mgmt. Systems and Purchasing ( ) Supvr. Licensing (X) Others R. Munz. 0AE Receipt Acknowledgement Required Yes No V If receipt acknowledgement is required, sign the following statement and return this form to the OQA Manager. The receipt of from: is hereby acknowledged. QDR No. Signed: ORidiNA AY h.:vv.,.. ,'
.Ui ,
l -
- Pago 1 of 2 )
Quality Deficiency Rep::rt RECNO I REV DATF g f RECTYPr 002-01 LOCATION FORMNO Aooo120s OLL-030-86 RETENTION PERMANENT Unit 1 QDR No. gpt a N-94, g8
- 1. INITIATION g initiatedby: Ralph F. Munz Dept:0A Engineerine Date/ Time)-M-86/1530 hW Dept: Plant Operations Notified (Date/ Time)' h fo 5, Responsibility:(Michael J. Ross1) Division 1 System Design Description for two-hour air supply for Requirement:
steam ar4 emergency systems controls, SDD #424-C Revision 1, Section 4.0 states in part, ~rnis moc111 cation is classified as important to safety." (2) TMI-1/FSAR. Update-4. 7/85. Section 9.10.3.2 undar "evn-hnne h a rtr un =<r ennn1# =*=e== h ~ . . -
"The compressed air supply will be of a moisture and particula'tec 'ontent eauni ti or better than that provided by the plant instrument air system." Further. TMI-1/FSAF ,
Update-4, Section 9.10.1.1 under " instrument and control mir syntam" arneae in nave "The function of the instrument and control air system in to continunnalv dalfvar clean, dry air at 100 psig (-400F dewpoint. filtered to 0.9 miernni. -"
^
/UJ54AR 84007/1/Mr Deficiency:
Contrary to the above requirements, (1) Puyftcase Order No. TP-035330, Blanket Purchase Order issued to cover the costs of providing TM1 with dry compressed air in bulk for Unit 1 two-hour backup air system. was issued with a safety classification of not important to safety by plant operations. (2) Purchase Order TP-035330 required the dry compressed air to have a dewpoint less than or eaual to
-100C at 100 psig. (-100C is equivalent to +140F) Further, no filtration require-ment was invoked. NOTE: No MNCR has been issued. Air Products & Chemicals, Inc.
was contacted by QA Engineering and Materials Management. It was verified verbally that the current tube trailer and any supplied to previous GPUN Purchase Order
#019430 were supplied from API's approved SQCL location in Camden. NJ. Gas was supplied identically as if Purhcase Order would have been classified (continued)
DELIVER TO OQA M ANAGER (SITE INITIATED)/QA ENGINEERING M AN AGER. CORPORATE (CORPORATE INITIATED) OR UNIT / GROUP SHIFT SUPERVISOR /SRO (BACKSHIFTS & WEEKENDS).
- 2. EVALUATION AND VALIDATION (IF EVALUATED AS POTssuTIALLY REPORTABLE, NOTIFY UNIT M ANAGEMENT: NOTIFY AND SEND COPY OF QDR TO LICENSING)
Date/ Time Received: % ML MM YES NO
'f ES NO YES NO
,f 10 CFR73 Potentially Reportable Under 10 CFR2O / 10 CFR50 10 CFR21 y 10 CFR71 j L.E.R. /
Evaluat By:
% A bE IM bM L cati Time
%~~ '
Name Titt) Unit Management Notified: uia Title cate Time Name
$ Licensing Notified: OYES 1260 Name Title c ate. Time 3
- Safety Significance:
Wimportant to Safety O Significant Notimportant to Safety 0 Not Significant Notimportant to Safety s {7 Justification (if Not Significant Not important to Safety): 4-21-86 Conf' ed A# tion Party: M. J. Ross to: 6 8, Corrective 130 cavs or s fro n e ponse e itt
) ). j
%/ / oate f
/
[} oOA-M QAE-MC , Aooo1209 A 36 FORw ARo TO RESyONSIBLE ACTION PARTY
m g
'
- l l
Deficiency (continued) QDR No. DLL-030-86 important to safety (same vendor's procedures apply). Also, dewpoint requirement would be equal to or better than -400F (current tube trailer was supplied at
-1280F at 100 psi) . Finally, all gases at the vendor are filtered to 0.1 micron.
API is forwarding letter to GPU attesting to this. i
)
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( 5. INTEGRATED CONTROL SYSTEM Babcock & Wilcox hYW $
- I i
,, 5. INTEGRATED CONTROL SYSTEM
- 5. 1. Function The integrated control system (ICS) is designed for a nuclear reactor supplying energy to parallel steam generators. The steam cycle consists of parallel feedwater pumps and flow control valves that con-trol the feedwater flow to each steam generator independently. There are crossover headers between the pumps, however, so that parallel steam generator operation at a reduced rating can be maintained with a single feedwater pump. Provision is made for by-passing some of the steam back to the condenser at low loads, thus providing a lower mini-mum flow operation and also a steam dump heat sink in the event of a
[ turbine or electrical load trip.
- 5. 2. De scription The control philosophy is developed recognizing, first, that each of the control variables has independent requirements and must be con-sidered separately; second, that all the variables must be coordinated into one system to produce automatic control.
- 5. 3. Control Concept There are two basic ways of controlling a reactor / steam gen-erator/ turbine generator unit. Reactor-following control is defined as the turbine controlling megawatts with the reactor / steam generator maintaining the required steam conditions and following an index of the unit load to maintain the required steam conditions. Turbine-following control is defined as the reactor / steam generator controlling megawatt generation and the turbine following this steam production to maintain the required steam pressure. Either of these basic control schemes can control the unit satisfactorily, but each has certain disadvantages k
and neither takes best advantage of the capabilities of both the steam 5-1 Babcock & Wilc0X
generator and the turbine. The integrated reactor / steam generator / turbine generator control for once-through steam generators has been designed to combine both of these basic control schemes in such a way that the advantages of both are accented and their disadvantages are minimized. Under abnormal operating conditions, the ICS can be con-verted to either of the two basic control schemes. The ICS takes advantage of the rapid, accurate steam pressure control available with the turbine-following approach. Steam pressure control is therefore assigned as the duty of the turbine valves. At the same time, the ICS achieves the rapid response to load changes avail-able from the reactor-following scheme by programmed borrowing and depositing of energy in the steam generator during transient conditions. The ICS thus provides improved unit stability by allowing a limited change in the energy stored in the steam generator during a transient and ensuring that normal steam pressure and temperature are restored at the desired megawatt generation after the transient has occurred. The basic requirement of the reactor / steam generator / turbine unit control is matching megawatt generation to unit load demand. The ; integrated reactor / steam generator / turbine control does this by coordi-nating the steam to the turbine and the rate of steam generation. To
~
accomplish this efficiently, the following basic reactor / steam generator requirements must be satisfied:
- 1. Balanced ratios of feedwater flow and Btu input to the .
feedwater are required to obtain the desired steam conditions.
- 2. Over-and-under Btu input control and over-and-under pumping are required to (a) compensate for changes in fluid and energy inven-tory requirements at each load; and (b) compensate for temporary deviations in feedwater temperature resulting from load change, feedwater heating system upsets, or transient final steam pressure operation.
The ICS organization comprises four independent subsystems: the unit load demand, the integrated master, the steam generator, and the reactor. The system philosophy is that control of the unit be achieved through feed-forward control from the unit load demand. The 5-2 Babcock 8 Wilcox
g, . ( unit load demand produces demands for parallel control of the turbine, reactor, and steam generators through respective subsystems, as shown in Figure 5-1. Figure 5-2 is a diagram of the integrated control system.
- 5. 4. Unit Load Demand Development '
- 5. 4. 1. Purpose The unit load demand development subsystem has two basic objectives. First, it must accept either an automatic or a man-ual demand for unit load (in terms of megawatts) from the load control systems and convert it to an analog signal compatible with the present state of the unit and its ability to change load. Second, in making this conversion, the subsystem must limit the unit; it must limit the unit load demand in both magnitude and rate of change based on both manually set limits and interlocks which represent limited operating capabilities.
- 5. 4. 2. Load Dispatch The load dispatch system sends increase or decrease puls e s . The discrete pulse signals represent a fixed increment of unit load demand. The input is a pulsed signal of 0.5 second pulse duration occurring at random intervals. The maximum continuous rate at which pulses can be sent is a 0.5-second pulse every 2.5 seconds.
The unit load demand is designed as a non-pulse stor-ing system. The ULD megawatt demand signal includes only those pulses to which the plant is capable of responding. All pulses or por-tions of pulses to which the plant has been incapable of responding before receiving additional pulses are rejected. The actual unit generation is sent to the automatic dispatch system as part of the area load control.
- 5. 4. 3. Unit Load Control Station A unit load control station panel is provided with the following functions,
- 1. Unit Load Manual- Auto pushbutton.
- 2. Unit Load Increase-Decrease pushbutton.
- 3. A maximum load limit sette r.
- 4. A minimum load limit setter.
, 5. A rate-of-change limit setter.
5-3 Babcock 8 Wilcox
l
- 6. A display of the desired megawatt requested by ADS or operator. /
- 7. Lights to indicate runback and/or limit con-('
ditions for turbine on manual control, ICS load limit, asymmetric rod pattern on the i reactor, RCP limit, FWP limit, NSS cross - limit. When the unit load control station is in the automatic control mode, the manual increase and decrease inputs are ineffective, and the load demand from the dispatch system or computer will pass to the load rate-of-change limiters. When the unit load control station is on manual, the load demand signals are introduced by the operator f'rom the control station. While a manual pushbutton is depressed, the target load demand will move in the direction selected until the button is released. Unit demand will then approach this target at the preset rate established by the operator or as the system demands, whichever is slower. Indicator lights provide the operator with analyses of the causes of limits or runbacks. All pushbuttons are "back-lighted" and/or split screen for operator intelligence of actions requested or accomplished. 5.4.4. I e ' umits Adjustable upper and lower limits are established by the operator from the control panel. Other limitations are produced automatically by the system in the event of certain unusual operating conditions. These unusual limits are applied by transferring fixed seti points whose output establishes an upper limit on load demand compati-ble with the state of the unit. The rate of change of this program can be adjusted manually up to 10% per minute (85 megawatts per minute), but it is automatically limited to be compatible with the speed of response of the unit. A 5% per minute rate limit (43 megawatts per minute) is imposed at the end of the load range, because the normal over-and-under pump-ing and Btu input are not possible in these ranges, so response is slower. When the unit load control station is in manual control, the same load limits (both magnitude and rate) apply. In this case, however, the op-erator can set the desired target unit load demand within the magnitude limits. The unit load demand will then be increased or decreased at the set rate until this target is attained. 5-4 Babcock & WilcoK
Maximum unit load can be limited automatically by the available reactor coolant flow, since there may be a gradual reduc-tion in this flow due to pump wear or other long-term factors. It is also p
, ossible that one or more reactor coolant pumps will either fail or not be available. A step change is introduced in the high load limit, depend-ing on the number of pumps available. Similar step changes in the high load limit are introduced in the event of an asymmetric rod or the loss , of one feed pump in operating condition.
- 5. 4. 5. Load Tracking Either manual or automatic unit control at the unit load selector represents essentially automatic unit operation for the balance of the control system. The refo re, if one or more of the lower-level control functions is in manual control, or if large errors develop between the demand and the variable, then unit load demand is made to follow the manual or limited control functions. To accomplish this function, generated unit load is substituted for unit load demand. When-ever unit maximum load is limited, or unit load demand is tracking the measured load, the manually set rate of change may not be compatible with the existing conditions. In such cases, a pre-established rate ac-ceptable for the existing conditions is transferred into the system.
The track mode of control is displayed to the operator by lighting both the manual and auto control lights on the front of the unit maste r selector station. During this mode of operation, the unit load control station is automatically transferred to follow the actual gen-erated load. Tracking will continue until the offending condition is brought back within the pre-established deadband. While the tracking mode is in progress, the rate-of-change limit is raised to maximum allowable levels. Following the termination of the limiting (tracking) condition, the unit load control station is returned to manual control. The operator will now have the ability to control load and, again, the manually set rate-of-change limit is effective.
- 5. 4. 6. Adaptive Control Large errors in paralleling the various control func-
\ tions will cause a unit load offset or error, which is undesirable.
i l 5-5 Babcock 8 Wikox
Therefore, the rest of the control system has adaptive control features which are designed to maintain the control in continuous proper calibra- , tion. The nature of these adaptive controls is such that they perform their calibration function during steady-state operation. Therefore, it is necessary to prevent the adaptive controls from operating during rel-atively fast load transients and for some time after such fast load tran- l
\
sients have occurred, thus ensuring that nearly steady-state operation will exist before the adaptive control is reactivated. These adaptive controls are known as " calibrating integrals." 5.4.7. Frequency The turbine-generator is equipped with frequency control capability in the forrn of governor action. In attempting to maintain constant turbine speed, the governor opens or closes the tur-bine valves, thus changing the measured megawatts and unit throttle pressure. These changes would normally be reflected to the measured variables of the analog control system and would result in errors. If nothing were done, the system would try to correct these errors, thus tending to counteract or fight the governor action. The governor action \ is applied on a strictly proportional basis between turbine speed and change in control valve position; it is normally set to a 5% regulation. In order to allow this unit to participate in frequency control, a similar proportional correction with range limits is added to modify the unit load demand to compensate for the changes that occur in unit load and pressure when governor action takes place. This frequency correction must be removed when the governor is ineffective, which is during the time when load limits are in effect, or when in the load-tracking mode. During these times, the frequency error signal is transferred to zero.
- 5. 5. Integrated Master Control Subsystem The integrated master control subsystem is a function designed to receive the demand for electrical generation from the unit load demand development subsystem and convert this to a demand for the reactor, the steam generator, and the turbine. This conversion recognizes the capabilities and limitations of the reactor, steam generator, and tur-bine. Since the reactor and the steam generators are not capable of 5-6 Babcock 8 Wilcox
producing rapid steam generation changes while maintaining coristant throttle pressure, and, yet, rapid load demands must be satisfied as quickly as possible, the turbine is used to provide the initial response. In so doing, the integrated control coordinates the action of the steam generator / reactor / turbine system. While in the integrated mode, re-sponse to load changes will be similar to reactor-following rnodes, yet stable pressure control will be retained.
- 5. 5. 1. Integrated Pressure Control Stable pressure control, a desirable feature of the turbine-following approach, is obtained by the pressure control applied to the turbine and turbine bypass valves. While stable pressure control is the feature of the turbine-following systems, its inherent response to load changes is a shortcoming in that the energy storage capacity of the steam generator is not utilized. Therefore, to harness the storage capability and achieve good response to load changes, the deviation between generated megawatts and desired megawatts or the megawatt
, error is used to modify the throttle set point.
When the throttle pressure set point is lowered during a load increase, the turbine valves will open to achieve the lower pres-sure, and, in doing so, will borrow energy from the steam generator to bring the turbine to a higher generation level in a shorter time than is possible without this energy storage. Similarly, the throttle pressure set point is raised during a load decrease, and the turbine valves will close to achieve higher pressure, and, in doing so, will deposit energy in the steam generator to bring the turbine to a lower level of genera-tion in a shorter time than is possible without energy storage. For any given load there is a finite amount of energy that can be borrowed from or deposited into the steam generator; therefore, the throttle pressure set point can only be altered in an amount equal to the available energy surplus or storage capability. Limits are established as a function of load to age capability and reflect the increase in energy storage with higher loads. Should the megawatt error exceed these limits, a further modification of the throttle pressure set point is not permitted; conse-quently, the controls have recognized that the turbine is no longer able to borrow energy from the steam generator or to store energy in the 5-7 Babcock 8. Wilcox
steam generator, and the turbine will follow the reactor and steam gen-erator, which are ultimately responsible for delivering the steam flow necessary to satisfy the generation demands.
- 5. 5. 2. Bypass Valve Pressure Control ,
Before the turbines are synchronized, turbine control will be on manual, and the bypass control valves are in the automatic , l mode. Pressure is controlled by the bypass valves at a pressure set point established manually. After synchronization is accomplished and initial load is applied to the turbine, the turbine control is placed on automatic, thereby releasing the turbine-to-throttle pressure control. As the turbine load increases, the bypass valve closes. Once the by-pass valve closes, the bypass system is biased up to a new set point which is approximately 50 psi greater than normal turbine header pres-sure. These bypass valves then serve as overpressure relief valves operating at the higher set point. A second overpressure relief setpoint is developed and also applied to the bypass valves. This control operates from individual steam generator pressure and is higher than the 50 psi (approximate) bias on throttle pressure. The resulting error is applied to the bypass valves through proportional action downstream from all the control components. Interlocks prevent the turbine bypass valves from opening on either low condenser vacuum or loss of condenser cool-ing water.
- 5. 5. 3. Other Modes of Control When the throttle pressure error exceeds permissible values, indicating that the turbine is no longer able to control the throttle pressure, or whenever the turbine control is placed in manual control, it is necessary to change from the integrated control to steam generator /
reactor-following control mode. Generation will then be established by the turbine, and the reactor and steam generator together become re-sponsible for throttle pressure control. At the same time, the unit load demand subsystem tracks generated megawatts to provide a feedforward to the steam gene rator/ reactor, and will resume control when the inte-grated mode is selected again. 5-8 Babcock 8 Wilc0X.
r . If the operator desires to control the unit in a turbine-following mode, he may do so by placing the steam generator / reactor control station in the manual mode and leaving turbine control on auto-ma tic. This mode establishes generation with the reactor and steam generators; the turbine retains the responsibility of throttle pressure control. The unit load demand subsystem tracks generated megawatts to resume control when the integrated control mode is again desired.
- 5. 5. 4. Feedforward Correction From Pressure Unit load demand is utilized as the feedforward demand to the steam generator / reactor and turbine while operating in the inte-grated control mode. Before this load demand can be meaningful as a steam generator demand, changes in the steam generator fluid and energy storage (caused by throttle pressure deviations) and any change in the steam generator / turbine-load relationship, such as turbine effi-ciency, must be accounted for. The deviation of throttle pressure from its setpoint is an index of fluid and heat energy utilized during load change; consequently, a factor proportional to this deviation serves as an index for the supply of feedwater required to return the fluid level in the steam generator to the correct value.
- 5. 5. 5. Calibrating Integral (Adaptive Control)
During steady-state operation in the integrated control mode, any megawatt error will, through a calibrating integral, be ap-plied to alter the demand on both the steam generators and the reactor on a gain and bias basis. This control action eliminates megawatt error by recalibrating the reactor and steam generator demand with respect to the unit load demand. With no megawatt error, the reactor and steam generator are producing the proper amount of steam for the demanded load. Once the proper calibration is established, no further calibration of the demand signal is required, unless (1) the turbine generator effi-ciency changes, (2) the enthalpy of the steam to the turbine changes, or (3) an error occurs in the feedwater flow measurement. The range of calibration change is limited to that necessary to compensate expected error due to these three points. 5-9 Babcock 8 Wilcox
Wh'en the throttle pressure error exceeds permissible limits, indicating that the turbine is no longer able to control the throttle pressure, or whenever the turbine control is placed in manual, it is necessary to change from the integrated reactor / turbine control mode to a reactor-following control mode. It then becomes the duty'of the reactor and steam generator to maintain the throttle pressure at the set point during steady-state conditions; thus, the throttle pressure error will be used by the calibrating integral instead of the megawatt error. A megawatt error exists for a short time after a load change due to the transient response of the unit, and any calibration during this time is undesirable. Therefore, when the load is changing faster than the predetermined rate, and for a short time after it stops changing, integration will be blocked by transferring zero error into the integral input; thus the calibration value that existed before the load change is maintained.
- 5. 6. Steam Generator Feedwater Control The steam generator control subsystem is a function designed to maintain the feedwater flow parallel with the reactor power level. i The steam generator demand signal is developed in the integrated master control subsystem by modifying the unit load demand by turbine header pressure deviation. This system also develops a control function for each steam generator and the feed pumps. The flow control is applied to the feedwate r valves'. The pumps control the pressure drop across the valves with a basic feedforward from total feedwater flow demand and a bias correction from differential pressure.
- 5. 6.1. Demand Development Feedwater demand is characterized from the error in feedwater temperature as compared to a feedwater temperature program from load. This characterization is required to compensate for the change in Btu input from the feedwater. If the feedwater tem-perature is low, then feedwate r flow should be decreased to increase the Btu per pound transferred in the steam generator, resulting in a 1 decrease in Btu per hour to the turbine. The primary purpose of this function is to maintain a constant Btu /lb of steam for large temperature i, 1
5-10 Babcock & Wilcox l l
e-- y errors, such as might be experienced on loss of feedwater heaters, etc. The characterized demand, then, becomes the master demand for total feedwate r.
- 5. 6. 2. Cross Limiting -
One requirement for proper steam generator oper.:. is that the feedwater flow / neutron power ratio must never exceed pre-determined limits. Whenever the feedwater control is on automatic, a set of limits is imposed on the feedwater demand to maintain the demand always within 5% of the neutron power. The temperature-com-pensated feedwater demand is biased 5% in each direction, creating a deadband for the cross-limiting control scheme. The cross limit of feedwater is taken from neutron error in the reactor control. Positive l 1 neutron errors indicate a deficiency of power with respect to the feed- ! forward demand and should put a high limit on feedwater. Negative errors, indicating excess neutron power, will run up the feedwater. If either limiting action on feedwater does occur, it I will be detected and will transfer the unit master to the load-tracking mode . The occurrence of this limiting action indicates that the neutron power is not able to satisfy its demand. Therefore, the control will maintain the rest of the unit (the turbine and the feedwater flow) in the proper relation to neutron power to maintain stable operation. For such a condition, the control is essentially in a turbine-following mode in that the load can be no greater nor less than 5% of the neutron power.
- 5. 6. 3. Steam Generator Demand Ratio The feedwater demand is ratioed between the two steam generators by changing the gain of the demand to one steam generator and subtracting it from the total demand signal. The resulting difference represents the demand to the second steam generator. This ratio con-trol is basically established by the operator, who has the ability to set the feedwater ratio manually (with limits of approximately 2.4:1) from the operating console. This ratio, however, is biased from the manual l set point by the ratio of reactor coolant flow to reactor inlet. temperature l diffe rential. In the event that a reactor coolant pump fails, the ratio of feedwater flow will automatically be redistributed proportionally to the 5-11 Babcock 8 Wilc0X l
.; steam generator in the loop with both pumps running. This redistribu-tion is done only up to the point where the 100% load capability of a , ' ~
steam generator is not exceeded. In so doing, the temperature drops across the steam generators will be balanced with the unbalanced flows. Since the reactor coolant supply to each stearn gener-ator comes from a common plenum above the core, the temperature of this fluid (T h) is the same for each steam generator. One of the goals of the feedwater subsystem is to maintain equal temperature distribution ) across the reactor core and equal steam temperatures to the turbine valve s. The reactor inlet temperatures from both loops are c.impared, and any difference biases the ratio control to redistribute the feedwater demand to bring both reactor inlet temperatures.back into balance. Thus, the temperature, imbalance across the core and to the turbine will be minimized. The automatic readjustment is blocked whenever both steam generators are placed on manual control, since each demand is set manually. l Although the ratio control acts to balance the return temperatures (T c), neither steam generator may exceed the operating I limits determined by the Btu available to it. This factor of available ' Btu is calculated from the reactor coolant flow available for each steam . generator characterized by reactor outlet and feedwater temperatures and the steam pressure of that steam generator. This loop capability signal is applied to the individual feedwater demand signals, thus rep-resenting an upper limit that the demand may reach.
- 5. 6. 4. Feedwater Valve Control
, The limited demand for each steam generator / feed-i water flow is then compared with actual, temperature-compensated, l individual loop, feedwater flow. The resulting error is applied through proportional plus integral control to establish the demand for valve i positions . The demand signal is then applied, through control stations, to both the startup and main feedwater valves. The valve arrangement is shown in Figure 11-5. These valves are sequenced into operation so
- that the startup valve opens first (from zero to about 15% load), followed l by the main feedwater valve.
/
5-12 Babcock 8 Wilcox
- __ _ _ , = - _ _ . _ _ _ . .-_- -
_ _ _ _ _ _ _ . _ . _ . - __. _ .- m _ 1 l
- 5. 6. 5. Steam Gene rator Level Control '
Valve position demand for each steam generator is , l limited in both the high and low directions from a level override or* lim-
~
iting signal, so that predetermined high and low level limits cannot be exceeded. At loads below 15%, it is nece ssary to control the steam generator level at a lower limit to mainte.in a minimum water inventory. j A high level limiting scheme at 100% is provided to prevent gross over-pumping of the feedwater.
- 5. 6. 6. Emergency Level Control )
An additional proviston a .ncluded in this control sys-tem to transfer to an auxiliary single-elervent level control upon loss of all four reactor coolant pumps to remov the core decay heat. Natural
, circulation of water through the reactor is >ufficient to keep the reactor temperature within prescribed limits if the steam generator level is maintained at a predetermined value somet . hat higher than that used in normal operation. This auxiliary level control is purposely simple and
[ operates with a minimum of equipment to accomplish its function, using a basic proportional plus integral control .op and the level scheme men-tioned above with a different low-level sespoint.
- 5. 6. 7. Feedwater Pump Control ,
To provide good characterization of the feedwater con-trol valves over an extremely wide flow range it is necessary to adjust feed pump speed to maintain a constant differential pressure drop across the feedwater valves. The differential across the feedwater valves is m.aasured for each of the two valve sets. The lower of the two is se-le cted and compared with the differential set point. The resulting error is applied through proportional plus integral control to increase or de-crease the basic feedforward from total feedwater flow demand. The basic pump control is taken as a feedforward from total flow demand, so that large or rapid load changes will move the pump speed accord-ingly, thus keeping the valve control within range. 1 5-13 Babcock 8 Wilcox j l I
- 5. 7. Reactor Control Subsystem
)
The reactor control subsystem is a function designed to control the reactor control rods in accordance with the reactor demand estab-lished in the ICS. This reactor demand signal controls reactor power ' in parallel with steam generator /feedwater flow. The relationship be-tween reactor power and unit load is not necessarily linear; therefore, a nonlinear demand signal can be introduced.
- 5. 7.1. Average Reactor Temperature Control The reactor demand is calibrated to produce a constant average reactor coolant temperature of 579 F. During startup, this av-erage temperature should be ramped from about 532 F to the normal av-erage temperature value, while the load is ramped from 0 to 15%. Be-low 15% load, the reactor is controlled manually. The normal operating temperature is set by the operator from the control console; it t.kes control when the reactor control station is placed in automatic. (See Figure 5-3. )
- 5. 7. 2. Calibrating Integral (Adaptive Control) (
A calibrating integral is used for steady-state correc-tion of average temperature. The integrated temperature error cali-bration is applied to the reactor demand first through bias and then through gain. At low loads, the predominant average temperature errors, such as the Btu added from reactor coolant pump losses or the efficiency of heat transfer in the steam generator, are likely to be fixed values. These are ofLet by the bias correction. As load increases, the predominant average temperature errors, such as the change in heat transfer efficiency or the change in feedwater temperature, are likely to be proportional to the load. These are calibrated out by the gain correction. This calibration is limited in magnitude to values within the expected range of such losses. When neutron demand range limits are in effect, or during load transients (as defined in the unit I load demand development subsystem), a zero error is transferred into the calibrating integral, thus holding the integration at its last calibration. 5-14 Babcock Si Wilcox
~
, 5. 7. 3. Cross Limiting The reactor demand assumes that the reactor and steam generator will respond in parallel. Any large feedwater errors indicate a failure of the steam generator to respond; thus the" system must be switched from feedforward to actual conditions. As seen in the feedwater control description, a complete set of cross limits would both increase and decrease the demand relative to the feedforward sig-nal. The reactor demand can only be decreased by cross limits, thus avoiding any reactor runups. The feedforward reactor power demand is biased up 5%, creating a deadband for the cross-limiting control scheme. The cross limit on reactor power level is taken from feed-water error. Feedwater error (for this purpose) is derived from the sum of the individual steam generator /feedwater flow errors. Positive -
errors indicate a deficiency of feedwater with respect to the feedforward demand; a positive error greater than the bias will run back the reactor demand. 5.7.4. Neutron Power Control In the reactor rod control, neutron power demand b, limited to a minimum of 10% and a maximum of 103%. This demand, when compared with the neutron power feedback from the nuclear instru- ' mentation, results in an error which is applied to the rod insert /with-draw relays. When this error exceeds a pre-established deadband, the rods are moved until the error is reduced to near zero. The polarity of the error determines whether the rods are inserted or withdrawn. An adjustable deadband is established to prevent unnecessary control rod movement from small demand changes and from spurious noise pickup. The control rod drives have a manual control mode independent of the control in the ICS. This control must be used when the power level is below 5%, and it may also be used during maintenance of the nuclear instrumentation or integrated control systems. Neutron error is monitored to prevent the transfer of the control rod drives from the rod-drive control at the rod drive to the ICS in the event that a large error exists. In the event of a loss of 5-15 Babcock 8 Wilcox
power to the ICS, an interlock will transfer the control to the local, manual rod drive control. l I ( 5-16 Babcock & Wilcox __ _. - -. - - \
Fih Figure 5-1. Integrated Control Systern Organization r-- l LFC
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_ .e 1 UNIT LOAO DENAND lNTEGRATED l l e r-- *- CONTROL +- q l l l l l 1 e I I e s : I 8 e I i e l l 8 ,_.l_ j k ' l ' s e e i TURBINE ' TURBINE I REACTOR BYPASS "" " l CONTROL lI CONTROL CONTROL I CONTROL I 1 s.._..* NOTES. 1 TURBINE CONTROL is A PART OF THE TURBlNE EQUIPMENT
- 2. LFC IS CUSTOMER'S LOAD FREQUENCY CONTROL l
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-- 850 5 0 15 20 IJO 60 80 100 Reactor Power, 7 REACTOR AMD STEM GENERATOR CHARACTERISTICS P STEAM GENERATOR OUTLET PRESSURE PhTURBINE HEADER PRESSURE I
i 5- 19 Babcock 8 Wilcox 1
3 l NEN ENGINEER TRAINING PROGRAM OVERVIEN, INCLUDING SPECIFIC REFERENCE TO ENERGENCY FEEDHATER AND INTEGRATED CONTROL SYSTEM. CONTACT: E.R. FREDERICK, TECH. STAFF TRAINING COORDINATOR CORPORATE TRAINING DEPARTMENT TNI EXTENSION 4022 O l l
~ ^
.R l l
Nuclear . GPU NUCLEAR CORPORATION up and Test, or Plant Analysis, for a variety of assignments. During this program the engineer wdl. as far as possible. 100 Interpece Paskwey be integrated into each technical group as though he/she Parsippany, New Jersey 07054 were a pennanen3 member and given chauenging assegs Locations: New Jersey and Pennsylvenia monts of a meanmgful nature. COMPANY BACKGROUND in addition to on-the fob training which will be offered by "N "* N"" " en training. n'" GPU Nuclear Corporation is a subsidiary of the General pecW a nnal e
- hing Public Utslities System, which provides some 32 bdlion kdo. course segments are being offered to educate engmeers watt-hours of electncity for about 1.6 millen customers supporting nuclear power plant operations ;
(more than 4 mdlion people) in New Jersey and Pennsylva-nia. GPU Nuclear Corporation is responsible for managing,
- Nuclear Energy Technology 1 operstmg, mamtaming, and providing technical support for
- Oyster Creek Systeras the System's nuclear generating stations.
- Three Mile Island Unit i Systems GPU Nuclear Corporaten was formed to provide full-time Near the conclusion of the two-year program, a permanent I dedicated management for the purpose of safe and effi. secten assignment will be made as a result of interviews ;
cient operation of all GPU-owned nuclear facdities, to pro. with several department managers vide uniform policies and operating cnteria for these ! facilities, to provide improved and ongomg in-house techn6- The following is a listing of technical groups participating in , cai support, and to elevate the stature of the nuclear oper. GPU Nuclear's Engineer Traming Program: ) ations within the GPU system. PARSIPPANY HEADQUARTERS (First Year Ass #gnments)
"**""9 GPU Nuclear manages the operation of the Oyster Creek Nuclear Generating Station in New Jersey; the start-up and l
operaten of Three Mde Island Unit I and the decontamina- lCR ast S t ngineering tion and recovery of Three Mile Island Unit II, both located
- Electncal Power and Instrumentation at Middletown, Pennsyfvania. Cff-site design and engineer.
- Engineenng Mechanics ing support and Headquarters management are located in
- Safety Analysis and Plant Control Parsippany, New Jersey.
- PM Analysis GPU Nuclear is a people-oriented company that places an unusualty high premium on the mdividual; your ideas, your l sk a
- Nuclear Licensing satisfaction and your achievement. We realize our most
- valuable resource is our staff of talented and dedicated , [,n "
n professionais--the key to our success.
- Engineenng Cost Analysis TWO-YEAR ENGINEER TRAINING PROGRAM OYSTER CREEK & TMI-1 PLANT SITES (Second Year Assignments)
The recent graduate with a BS or MS degree in Electrical, Mechanical, Chemical or Nuclear Engineering wdl have the l h;','n't Ch ist opportunity to exponence several different functional fields
- Maintenance Engineenng in the Engineer Trainmg Program. The upose of this pro-
- Operations Engineenng gram is to stimulate interest and dovesp career growth
- Radiological Engineenng potential for the new engineer.
- Plant Analysis The initial six month assignment will be into a technical c i n group located at our Headquarters in Parsippany, New Jer-sey. Dunng this time. the engineer wdl be given a variety of BENEFITS technical assignments in his/her area of engineer training under the supervision of senior engineenng personnel. GPU Nuclear offers the newly hired graduate a comprehen-srve benehts package which includes the fodowing:
The second six-month assignment wdl also be in Parsip.
- Medical Insurance pany, New Jersey. Dunng this penod, the engineer wdi be
- Dental Insurance assigned to a functionally different technical group, which
- Life Insurance would likewise utilize the engineer's technical skills in a e Travel Accident Insurance vanety of assignments.
- Disabdity insurance
- Pension Plan The second twelve month period wdf be at either one of
- Savmgs Plan GPU Nuclear's nuclear plants, i.e.. Oyster Creek in Forked
- Sick Leave
. River, New Jersey or Three Mile Island Unit I near Harns-
- Vacation burg, Pennsytvania. Durmg this period, the engineer wdl be
- Holidays ,
assigned to one of the on-srte technical groups, e.g., Main-
- Educational Assistance tenance, Operations, Plant Engineenng, Chemistry, Start-
- Credit Unen 1
1 NEN ENGINEER TRAINING INTEGRATED CONTROL SYSTEN- TNI-1 ( ICS IS NOT CURRENTLY TAUGNT AT THE INTRODUCTORY LEVEL FOR ENGINEERS TRAINING IS DGNE ON TNIS SYSTEM ON AN AS HEEDED BASIS (DETERNINED BY ENG. MANAGEMENT) AND USES CLASSES / TAPED COURSES PROVIDED FOR OPERATORS, TNIS NOULD INCLUDE SINULATOR TRAINING FOR SELECTED ENGINEERS. (.
e e EMERGENCY FEEDilATER SYSTEM - TRAINING OBJECTIVES
- 1. List the functions of the system.
- 2. Describe, in words, where the emergency feedwater inlet nozzles are located in the OTSG and why this location is necessary.
- 3. Describe, in words, how natural circu1ation through the OTSG is established following the loss of all reactor coolant pumps.
- 4. Describe, in words, the function of the cavitating venturi and how it accomplishes its function.
- 5. List in order of preference the sources of water to the ERI system.
- 6. Explain the concept of boiler / condenser in regards to the OTSG.
- 7. Explain how the RCS high point vents can aid in establishing natural circulation flow.
l l l l l
. o c) All 3 emergency feedwater pumps will receive an auto start signal upon a loss of all feedwater pumps or on a loss of all 4 reactor coolant pumps.
- 2) Emergency feedwater Regulating Valves (EFW-V30A/B) a) Can De controlled oy either tne ICS system (auto) or manually from the control room o) Used to control the flow of water to the OTSG to control water level c) Air operated from all 3 air systems
- 3) Cavitating Venturis a) Venturis were installed to prevent excessive loss of water from tne feed system in the event of a steam line or feedwater line rupture . !
l If one of the OTSG developed a major steam leak, level in tnat generator would decrease rapidly. Tne ICS system would sense the level drop and open EFW-V30 to try to maintain generator level. Tne venturi will limit tne flow to the affected generator to:
- 1. Limit the pressure buildup within the reactor building due to tne steam released from the rupture
- 2. Prevents possfole restart of the reactor due to a large drop in primary coolant temperature.
- 3. Limit the flow of EfW to a ruptured OTSG in order to ensure sufficient EFW flow to the intact OTSG.
l
, 5) Isolation Valves EF-V1A/8 and EF-V2A/B Motor operated valves tnat can be used to isolate and split tne emergency feedwater suction and discharge headers. Yalves controlled from the control room.
D. Sources of Emergency Feedwater
- 1) Normal Source i
a) Coadensate storage tanks
- 1. Each tank contains 265,000 gals. maximum 150,000 gals. minimum
- 2) Alternate Sources (in order of preference) a) Main condenser notwell - 165,000 gallons o) Million gallon demin. water tanx (via tne notwell) c) River water - last choice E. Normal Operations The emergency feedwater system provides no function during normal plant operations.
F. Emergency Operations I) System Actuation a) The system uses 2 actuation channels; ' A' and 'B'
- 0) Eacn enannel senses ooth reactor coolant pump monitor and main feedwater pumps differential pressures.
1 1
- 3) Natural Circulation
~ a) The greater the difference netween the thermal center for heat generation and tne thermal center for heat removal, the greater tne force of natural circulation, due to the larger density dif-ferences. Tnis is wny on loss of all RC pumps tne ICS system will automatically maintain the OTSG 1evel at 50%. By doing this tne tnermal center of neat removal will oe higher and a greater natural circulation will occur. o) OTSG Levels
- 1. l.oss of main feedwater pumps Tne ICS will maintain OTSG 1evel at 36" aoove the lower tube sne t.
- 2. Loss of all 4 RCP's The ICS will maintain the OTSG 1evel at 50% of its operating range. This corresponds to a level of 248" aoove tne lower tuoe sheet.
- 3. Loss of all 4 RCP's with only one OTSG availaole for heat sinx removal.
Tne CR0 must manually maintain the water level in the operating OTSG at a level of 9b% of its operating range. Tnis is a level of 379" above tne lower tube sheet. This allows for an increase in natural circulation in the operating OTSG. 6
H. System Control from the Control Room
- 1) EF-V30A/B each have 2 means of control in the control room a) Normal control (1) when in auto the ICS will control tne valve position from 0-100% open (2) When in manual, the CR0 can control valve position fron 0-100% open In oath cases (1) and (2) tne power supply for valve control is ATA vital ous, c) Backup control - This is to allow the operator control of the valve. No auto ICS feature. Control position from 0-100% open.
Power supply is ATd vital cus.
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S ction B-4 R:visien 0 FIG U R E-19 OTSG EMERGENCY PEEDWATER HEADER OT5G SHELL EMEMENCY - F EE DW AT E R SUPPLY .
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Levels in the OTSG for Emergency Feedwater Operations i PRIMARY COOLANT IN LET Y runnunnssnus ggn. OPERATING HEIGHT ABOVE RANGE LOWER TUBESHEET (%) (INCHES) 100% - - - - - - - - - - - 394" 95% - - - - - - - - - - -
- 379" i
50%- -- - - - - - -- - 248" i 0%- - - - - - - - - - - 102"
- - 30" LOWER 1U.ESHEET
)v( PRIMARY COOLANT OUTLETS t
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FIGURE 3 CAVITATING VENTURI - l l a o , FROM L ( M1 ' 2 ,
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The cavitating venturi is used to limit flow through the line. As' water passes through the cavitating venturl it is ac. celerated as the venturi narrows (point 1). This causes a low pressure area to be developed at point 1. When the pressure at point i reaches the vaporization pressure of the water, the water will flash (cavitate) which chokes off flow. t l \ 4 s
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SECTION I-1 REVISION O TMI-1 OPERATIONS PLANT MANUAL EERTNCY FEEDWATER Table of Effective Pages PAT REVISION PAT REVISION PAT REVISION PAT REVISION 1 0 2 0 3 0 4 0 5 0 6 0 7 0 8 0 9 0 10 0 11 0 12 0 13 0 14 0 15 0 16 0 17 0 18 0 '- 19 0 20 0 21 0 22 0 23 0 24 0 25 0 Concurrea Autnar .'. '. 7 % 4+ c ' U l Date i : - : .s - Owner / /m Date /2 - C Fr Operator Training Manager, TMI-1
, J 0 .,
,_ s AinM(4- Date d'f"EJ Training Coordinator, TM1-1 \1. Sa b E L. .- Date t /i / 6V Approved
%/ /
Mana r, Plant Operations (
, g
(/
SECT 10f. 1-1
. REVISION O
- 1. REFERENCES R = Reprodace.
D = Oefend or explain given the figure A. System Description
- 1. Emergency Feed Water B. Drawings
- 1. CAI-302-011 Main Steam
- 2. GAI-302-081 Feedwater
- 3. GAI-302-081 Emergency Feecwater
- 4. GAI-302-051 Auxiliary Steam C. Manufacturer's Instruction Manuals
- 1. Worthington Manual on Punps and Steam Turbines
- 2. Westinghouse Motors
- 0. Procecure
- 1. 1106-6 Emergency Feec 2.
- 3. 1202-26A Loss of Steam Generator Feed to Both LTSG's 1202-37 Coolcown from Outside The ccntrol Room E. TMI-I FSAR SEcticn 10.6 - t.mergency Feecwater System F. TMI-I Technical Specifications
- 1. Section 3.5.5 Accident Monitoring Specifications
- 2. Section 3.4 Decay Heat Removal, Turbine Cycle
- 3. Section 4.9 E.F.h. Pericdic Testing 0559K
SECTION I-l REVISION O III. INTRODUCTION The emergency feedwater system consists of two motor-driven pumps powered from redu, dant Class 1E 4160-V buses and cne 100-percent-capacity turbine-criven pump which receives steam from the main steam lines or the auxiliary steam line. Both of the motor-driven pumps and the turbine driven emergency feedwater pumps will automatically start on loss of both main feedwater pumps or less of all four reactor coolant pumps. The motor criven emergency feedwater pumps are automatically loaded on the diesel generator during 1 css of offsite power with or without simultaneous existence of an ESAS actuation. The three punps are located in the Intermediate Building. The turbine-driven pump is physically separated from the motor-driven units. The emergency feedwater punps take a suction, thrcugh separate lines, frcm the two condensate storage tanks. The condenser hotwell can also be used as a suction to the emergency feedwater pumps. If the ccncenser hotwell decreases, the million gallon tank can be lined UD to the hotwell. If all the water on site is used up, river water can be used via the Reactor Building emergency cooling water pumps. Each of the condensate storage tanks has a level incication and two level alarms. One alarm is at the technical specification limit for emergency feedwater which set is at 11.5 feet (150,000 gallons) ano the other is set at approximately 5 feet to alert the operator that there is 20 minutes of punpable water lef t in the condensate storage tanks at the energency feecwater design flow rate. Each emergency feedwater punp is protected by recirculation lines back to the "B" concensate storage tank. The three emergency feedwater pumps discharge into a connon header from which separate G-in. lines deliver water to each steam generator. Each of the 6-in. supply lines contain a flow-limiting ve7 turi ano an air-operated control valve controlled by ICS. The ICS controls energency feeawater flow after the emergency feedwater pumps have been started. IV. SYSTEM FUNCTIONS The emergency feedwater system celivers water to the steam generators curing loss of both main feedwater pumps or less of fcur reacter coolant pumps for the purpose of (1) removing decay heat anc (2) provicing a smooth reactor coolant transition from reactor coolant pump operation into natural circulation. 0559K
SECTION 1-1 ' ALVISION G Suction is shifted to the condenser hotwell when the condensate storage tanks level reaches 1 foot. When ccncenser hotwell level reaches 5 feet, sucticn is shif ted to the million gallon oemineralizea water storage tank via the condenser hotwell. River water is not useo unless it is absolutely necessary. The emergency feed pumps then discharge into the respective OTSG via separate lines. Flow through the lines are controlled by the D -V-30A and 0 -V-308 valves. The EF-V-30A and 0 -V-308 valves are normally controlled automatically by the Integrated Caltrol System. Emergency feecwater control valves, 8 -V-30A and D -V308, can also be controlled frem the remote shutdown panels, which are located outside the control room, if the Control Room has to be evacuated. Upon loss of both main feedwater pumps, level will be automatically controlled at 30" on the OTSG start-up level indication. On a loss of all four reactor coolant pumps, the level will be automatically controlled at 50% cn the LTSG operating level. Before the energency feedwater enters the OTSG it must pass through the cavitating venturis. Their functicns are listeo in Section IV of this document. The emergency feedwater enters the OTSG ti..cu@ the emergency feed ring which is located high in the OTSG. The emergency feed ring has seven feed nozzles, but one of the nozzles is blocked to prevent thennal damage to the OTSG lower tubesheet. The blocked nozzle directed emergency feed into the OTSG inspection lane which provided a direct patn te the bottom tubesheet. The high location of the feed ring provides a higher thermal center in the OTSG which aids in establishing natural circulation flow. The feed nczzles each contain a thermal sleeve to minimize the thermal shock to the nozzles when cold emergency feetwater is injected into the OTSG . M i e 0$$9K
SELTION I-1 REVISION O The turbine driven punp is located in the Intermeolate Building in a separate compartment on the 295' ficor elevation. The turbine driven ptnp is physically separateo from the two motor driven units. The pump uses a minicum flow by-pass orifice with a locked open bypass valve. This recirculation line joins those from the two motor driven , feedwater ptmps and is directed to condensate storage tank 6. Power to the turbine oriven pump is from the safety relatec portion of the main steam system or the auxiliary steam system. The two motor driven emergency feedwater pumps are Worthington Model 2-1/2 WTF-108, eight (6) stage, horizontal split case, diffuser centrifugal pumps. Each of these pumps have minimum flow by-pass orifices and the fo11cwing oesign data: , Capacity (GPM) . . . . . . . . . . . . . . 460 Minirom flew (GPM) . . . . . . . . . . . . 84 Total Dynamic Head (f t.) . . . . . . . . . 2700 Speec (RPM) . . . . . . . . . . . . . . . 3570 Tenperature Range (cF) . . . . . . . . . . 40 - 110 Specific Gravity . . . . . . . . . . . . . 1.0 N3SH required (ft. ) ........... 16. 0 BHP requirec . . . . . . . . . . . . . . . 450 Efficiency (1%) . . . . . . . . . . . . . 6 9. 5 Critical Speed (RPM) . . . . . . . . . . . 7050 Suction Flange (inches) ......... 4 Discharge Flange (inches) . . . . . . . . 2.5 The motor driven feedpumps (2A and 18) are located in the Intermediate Building east of the turbine driven pump in a separate compartment on the 293' floor elevation. All three emergency feedwater pump suction lines contain Mack, BT-W 6 inch carben steel strainers of 150# butt weld construction. The emergency feedpump 1A turbine and ptmp bearings, together with the emergency feedpump bearings of pumps 2A and 28 are provided with a cooling system of retirculated feccwater from the pump discharge to the pump suction. The EFW ptmp motors are Westinghouse type CSP, horizontal, l squirrel cage, induction, drip proof with split sleeve bearings with the following characteristics: 450 H.P., 3600 R.P.M., 4000 volt, 3 phase, 60 cycle. These ptmps have space heaters proviceo in the motors to eliminate concensation. l
~
\
0$$9K
SECTICN I-1 REVISION O feedwater system controls to previce the motive force air for valves MS-V-4A/B, MS-V-6, EF-V-3CA/B shoulo the normal plant instrunent air conpressors ano the backup histrument air compressors be lost. Transfer to the two hour backup air supply is also autcmatic anc no operator action is required.
- c. Failure Modes
' The emergency feedwater contrcl valves EF-V-30A/B will f ail open on loss of instrument air and fail half cpen en
, loss of control power.
- d. Valve operation of D:-V-30A and EF-V-308 D:-V-30A and D:-V-308 are located in the motor driven emergency feed pump room.
There are five moces of control on 8 -V-30A anc EF-V-300. These modes are:
- 1. Ncrmally the valves are centrolleo sutomatically ty the Integrated Control System (ICS).
- 2. The valves Can be Controlled via the ICS by using the D -V-30A and 8 -V-3C8 hand / Auto station. Tne staticn nust be placed in tne Hand pcsition and valve position is controllea by the toggle pwitch on the Hand / Auto station for EF-V-30A or EF-V-308.
- 3. There is a back-up controller for the valves in the .
centrol room. To use this controller, the resoective control switch (console left for EF-V-30A and Console center for 8 -V-308) must be placed in the "back up" position. Valve position is then controlled from the back up controller. 4 The valves may be controlled from the Remote Shutoown panels which are locateo on the secena floor of the control tower. To establish control at the remote shutccwn panels there are panal switches which must be operatec. Tnese panel switches are locatec as follcws: D:-V-30A - 3rd floor of the centrol tcwer in the ESAS relay room near the east wall. 07-V-308 - 2no ficar or the centrol tower in tne remote shutcown panel rcon en the west wall. 05$9K
SECTICA I-1
, f,EVISION O MS-V-13A and MS-V-138 are located in the steam driven emergency feed water pump rocm. MS-V-13A will open en an "A" emergency feedwater actuation signal to acmit steam to the steam driven emergency feedwater pump turcine.
Likewise, MS-V-138 will open on a "B" emergency f eecwater actuation signal to aonit steam to the steam oriven emergency feedwater punp tureine.
- g. Valve Operation of MS-V-10A and MS-V-108 MS-V-10A and MS-V-108 are located in the steam driven emergency feedwater pump room. These valves are bypasses arome MS-y-13A and MS-V-138. They are used to supply steam to the steam driven emergency feeawater pump turbine when steam pressure gets too Icw to adequately supply the steam turbine through MS-V-13A and MS-V-138 alone. MS-V-10A and MS-V-108 are jog contro11eo valves
$1ch are operated from the control room on console cmter.
- h. Valve Operation of EF-V-8A, EF-V-88, and EF-V-8C Due to earthquake consicerations EF-V-8A, EF-V-86, and EF-V-8C are aoninistratively failed to the open pcsition for maximum recirculation. ,
EF-V-8A and EF-V-8C are located near their respective motor driven emergency feedwater punp (EF-P-2A and EF-P-28 ) . EF-V-8B is located near the steam driven emergency feedwater pump (EF-P-1). 4 Cavitating Venturi The cavitating venturl's are located near the "A" motor criven energency feedwater pump. They are in the northeast corner near the ceiling. Figure 3 contains an explanation on how the cavitating venturi works. 0559K
SECTION I-1 REVISION U l E. To prevent water carry over into the main steam lines, trip all operating emergency feedwater pumps at an OTcG 1evel of 95 percent in the operate range during normal or emergency operation. (This guidance does not apply when performing a flooded nozzle heat-Lp or cooldown operation.) F. Following actuation of the 0 W system, an operator must te sent to the EF-V-30's area and establish communications with the Control Room. This action is necessary to ensure proper operation of the I system and enhance the response time should manual system operation be required. G. The emergency feed pumps will not be used to replace a main feed pucp for normal operation. H. EFW THROTTLLNG CRITERIA To prevent RCS overcooling due to excessive feed rates, manually control emergency feedwater flow as necessary to maintain OTSG pressure within 100 psig of desired pressure. Monitor RCS cold leg temperatures to ensure feed rate is not causing a significant RCS tenperature transient. Sufficient flow must be maintained to remove RCS heat and promote circulation. Anytime 0 W flow is actuated and automatically increases steam generator level to 50% on the operating range, it can cause significant RCS overcooling. In order to reduce the possibility of thermal cycling of the emergency feedwater nozzles, positiordng of the emergency feedwater centrol valves (0:-V-30A/B) to the fully closed position should be avoided during the manual control of emergency feedwater flow. Overcooling can result when 0W injects cold water into the OTSG at high flowrates, when trying to obtain the OTSG 1evel setpoint. When the level in:reases too rapidly the inventory accumulation is 3 colcer heat sink tnan is required to remove core decay heat'. Steam pressure drops and the RCS is overcooled. During forced flow, this is cuickly reflected in cold leg tenperature and RCS pressure. During natural circulation the RLS indications are delayed several minutes due to the slower loop transport tine and are therefore not suitable parameters to use for feedrate cont rol. Steam generator pressure is the preferred paraneter since it responds rapidly to EFW flow changes under forced ficw and natural circulation. Use of this single parameter permits simplified guidelines. Addition of EFW at the maxinum rate is not needed to achieve stable natural circulation of the RCS. However, continuous flow is required to the OTSG to maintain the high thermal center in tne UTSG for natural circulation of the reactor coolant water. l l l 1 0559K l
SECTION I-l
. REVISION O H. 2 Hour Air Bottles - This system is a series of high pressure air bottles which are located in the "A" Diesel room. If the instrument air system cannot supply sufficient air pressure, the 2 hour air bottle will automatically supply the following valves associated with the emergency feecwater system:
OF-V-30A D -V-308 M S-V-6 MS-V-4A MS-V-48 IX. TECHNICAL SPECIFICATION A. The reactor coolant system cannot be heated above 2500F with irradiated fuel in the core unless the follcwing components in the emergency feedwater system are as follows:
- 1. The turbine driven emergency feedwater pomp and twc nalf-sized motor driven emergency feedwater pumps are operable.
- 2. System piping and valves associated with the above components are operable, e 3. Any component cited above may be removed from service for purpose of maintenance for a period not to exceed 48 nours.
If this period is exceeded, the unit will be placed in cold W1utdown within 12 hours.
- 4. As a minimum, one channel of emergency feedwater flow instrumentation for each flow path shall be operable.
- 9. Emergency Feedwater Pumps Periodic Testing
- 1. Applicability Applies to the periodic testing of the turbine criven ano two motor driven emergency feedwater ptmps.
- 2. Objective To verify that the emergency feedwater pumps and associated valves are operable.
v 0559K [
FIGURE-1 EMERGENCY FEEDWATER _= % - 8A CONDENSATE
\_
TANK B HOTWELL ( us %s v 2A EMERGENCY 3OA i FEEDWATER " CAviTATING 2A
- 1B "
PUMP 5 VENTUR.1 river _" / ( WATER / \ I 1A 2B 86
, ms %s v n n n n
(- VE TU A i "' % HOTWELL
> 28 l CONDENSATE f O O :=
TANK A /- O T T 5 S G
< X ,
o 8C y CONDENSATE STORAGE v v f TANK B DE-ICE LINE
SECTION 1-1 REVISION O FIGURE-3 CAVITATING VENTURI
. e ' o e *
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, '2e o -
- FROM E FP's a '
TO
^ *
,w ,, OTSG's 2,% * -
o a..... .
, o .
The cavitating venturi is used to limit flow through the line. As water passes through the cavitating venturi it is accelerated , t as the venturi narrows (point 1). This causes a low pressure area to be developed at point 2. When the pressure at point 2 reaches the vaporization pressure of the water, the water will flash (cavitate) which chokes off flow. l l l 1 1 l
l F I G U R E-5 EF-V30 A/B CONTROL AIR SOURCES i l l- INSTRUMENT AIR AIR TO CONTROL THE CONVERT ER BACKUP AIR % 2 HOUR BOTTLE AIR i J INSTRUMENT AIR
' y Al TO ACTUALW BACKUP AIR REPOSITION THE VALVE O
2 HOUR BOTTLE AIR , E F -V-30 A/B 55 an oE
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- RING Oz 23 I tlNE sag. COVER G 2 SIUfflNG SOE GA5EEI I 33 4 4 gapggggs weg," 172 3' $ NAP SING "'*
GP l ltAL. HEAD DISC GASEET AlHG NOlt s O oni.e.es meeked l') nee las I. e me ge p.mp only. For p.mps having moes stages. Ihese qeontisies are inceensed occeed.agly.
1 TABLE 1 ilME FOR EMERGENCY FEEDWA.TER PUMPS TO REACH FULL SPEED START TIME TO FULL START EVENT TIME TO FULL SIGNAL EFPI SPEED EFPI SIGNAL EFP2 SPEED EFP2
~
LOSS OF FW OR LOSS OF RCP lMMEDIATE 18 Sec. 5 Sec. 15 Sec. LOSS OF FW OR IMMEDIATE 18 Sec. 15 Sec. 25 Sec. LOSS OF RCP AND LOSS OF OFFSITE POWER s LOSS OF FW 3 OR lHMEDIATE 18 Sec. 20 Sec. 30 Sec.
, LOSS OF PCP i AND j ESAS LOSS OF FW OR LOSS OF RCP lMMEDIATE 18 Sec. 30 Sec. 40 Sec.
AND ESAS AND LOSS OF
- OFFSITE POWER I AN 54-oS
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a HEM ENGINEER TRAINING EMERGENCY FEEDHATER SYSTEM- THI-1 (INTRODUCTORY) AUTHOR: HAYNE HAYLOR; CORPORATE TRAINING, PARSIPPANY, N.J. I i i
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. 4 (ol) b EMERGENCY FEED!lATER SYSTEM - TRAINING OBJECTIVES
- 1. List the functions of the system.
- 2. Describe, in words, where the emergency feedwater inlet nozzles are located in the OTSG and why this location is necessary.
- 3. Describe, in wc?ds, how natural circ Tation through the OTSG is established following the loss of all reactor coolant pumps.
( 4. Describe, in words, the function of the cavitating venturi and how it accomplishes its function.
- 5. List in order of preference the sources of water to the ERI systen.
- 6. Explain the concept of boiler / condenser in regards to the OTSG.
- 7. Explain how the RCS high point vents can aid in establishing natural circulation flow.
9
- se
c) All 3 emergency feedwater pumps will receive an auto start signal upon a loss of all feedwater pumps or on a loss of all 4 reactor , coolant pumps.
- 2) Emergency feedwater Regulating Valves (EfW-V30A/B) a) Can oe controlled oy eitner tne ICS system (auto) or manually from the control room o) Used to control the flow of water to the OTSG to control water level c) Air operated from all 3 air systems
- 3) Cavitating Venturis a) Venturis were installed to prevent excessive loss of water from
{ tne feed system in the event of a steam line or feedwater line rupture . . If one of the OTSG developed a major steam leas, level in tnat generator would decrease rapidly. Tne ICS system would sense the level drop and open EFW-V30 to try to maintain generator level. Tne venturi will limit tne flow to the affected generator to:
- 1. Limit the pressure buildup within the reactor ouilding due to tne steam releaseo from the rupture
- 2. Prevents possiole restart of the reactor due to a large drop in primary coolant temperature.
- 3. Limit tne flow of EfW to a ruptured 0TSG in order to ensure sufficient EFW flow to the intact OTSG.
t
- 5) Isolation Yalves EF-Y1A/d and EF-V2A/B Motor operated valves tnat can be usea to isolate and split tne i emergency feedwater suction and discharge headers. Yalves controlled from tne control room.
D. Sources of Emergency feedwater
- 1) Normal Source a) Condensate storage tanks
- 1. Eacn tank contains 265,000 gals. maximum 150,000 gals. minimum
- 2) Alternate Sources (in order of preference) a) .4ain condenser notwel1 - 105,000 gallons a) Nillion gallon demin water tang (via tne hotwell) c) River water - last choice E. Normal Operations Tne emergency feedwater system provides no function during normal plant operations.
- F. Emergency Operations l
- 1) System Actuation a) The system uses 2 actuation channels; ' A' and 'B' o) Eacn enannel senses ootn reactor coolant pump monitor and main feedwater pumps differential pressures.
-4_
i
4
- 3) Natural Circulation a)
Tne greater the difference oetween tne thermal center for neat generation and tne thermal center for heat removal, the greater tne force of natural circulation, due to the larger density dif. ferences. Tnis is wny on loss of all RC pumps tne ICS system will automatically maintain the OTSG level at 50%. By doing this tne tnermal center of neat removal will oe higner and a greater natural circulation will occur.
- 0) OTSG Levels
- 1. Loss of main feedwater pumps The ICS will maintain OTSG 1evel at 36" aoove the lower tub sneet.
- 2. Loss of all 4 RCP's Tne ICS will maintain tne OTSG level at 50% of its operating range.
Tnis corresponds to a level of 248" aoove tne lower tuoe sneet. 3. Loss of all 4 RCP's witn only one OTS5 availaole for neat sink removal. Tne CR0 must manually maintain tne water level in tne operating OTSG at a level of 96% of its operating range. Tnis is a level of 379" aoove tne lower tube sneet. Tnis allows for an increase in natural circulation in tne operating OTSG. 6
H. System Control from tne Control Room
- 1) EF-V30A/B eacn nave 2 means of control in the control room a) Nonnal control (1) when in auto the ICS will control tne valve position from 0-1001, open (2) When in manual, the CR0 can control valve position fron 0-100% open In ooth cases (1) and (2) tne power supply for valve control is ATA vital ous.
o) dacKup ce;strol - Tnis is to allow the operator control of tne valva. No auto ICS feature. Control position from 0-100% open. rower supply is ATd vital ous. ( hkup poemal I o e Av+o m u ual l I I l 1 1 I I l_ - - . _ . . ____) so s. , to CeWo\ lleem l l L _ _ _ _ _ _ _ + To EF-V3o A/e conito\
-8
r ' i j EMERGENCY FEEDWATER SYSTEM s.h. 2 dxw jg [ .7 CAVITATING ! I 30A i
- dk R M "
28 2A JL RECIRC rs 4 es q l BA N 4 i L.D. 88 STSG OTSG
- SC l L.O.
2B N EMERGENCY i 1 2A + FEEDWATER ( y ( PUMPS N ( g N g N ( JL 18 JL 1A J L
- 3 2 7
! V ' TO COIDENSATE FROM CONDENSATE FROM RIVER FROM CONDENSATE j STORAGE STORAGE TANK B WATER STORAGE TANK A , TANK 5 DEICE LINE I
,.. PRIMARY INLET N0ZZLE 4-e g =
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. 7 iCl ]
AUXILtARY FEEDWATER HEADER
& INLET CONNECTIONS Na n=
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= -;. i STRAIGHT TUSES -- m .- ,) :
EF . l l
. _ j STEAM OUTLET N0ZZLE 4 h-e
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- 1 E
FEEDWATER HEADER & INLET , l ( c.CNNECTIONS .,
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% t Figure 1 - 1 Once Through Steam Generator
. \
53ction B-4
^
Revision 0 FIG U R E- 19 OTSG EMERGENCY FEEDWATER HEADER 1 I OTSG SHELL EVERGENCY F EE D W AT E R SUPPLY
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e l i g_EMEg 3 NOZILE g ; l CONMECTION
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/
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a'
// _ ,.
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- E X T E RIOR EMERG.
FEEDNATER HEADER EMERG. FEEDWATE R NOZZLE AT THIS LOCATION REMOVED
& SLANK FLANGED
~
G h
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*2 NOT TWERNAL FLul0 CENTER FOR COLum COLO HEAT REMOVAL FLUID
[L COLUM , ' h f J) [- __ (g l l l
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- . - --- - - -., g '- THERWAL CENTER FOR MEAT ADDITION Mg /
y g N W
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driving head "eff IP c - P g)
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4 Levels in the OTSG for Emergency Feedwater Operations PRIMARY C0dLANT IN LET Y twwww/w//m ggg, OPERATING HEIGHT ABOVE RANGE LOWER TUBESHEET (%) (INCHES) 100%.- - - - - - - - -- 3 94" {- 95% ~ - - - - - - - - -- 379" 50%--- - - - - - ^-- 248" 0%-- - - - - - - - - 10 2 " ! -- 30" l ' LOWER TU.ES m 1
)v PRIMARY COOLANT GUTLETS l
l . . .. l r
9 FIGURE-3 CAVITATING VENTURI
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FROM g (% C 2 g.o . a o ,
, W, , fh*
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MI ' * * * *'
- EFP ' " ;
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= ,o
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. o . . ,
o , , ( ihe cavitating venturl is used to limit flow through the line. As water passes through the cavitating venturl it is ac-celerated as the venturi narrows (point 1). This causes a low l pressure area to be developed at point 1. When the pressure at point 1 reaches the vaporization pressure of the water, the , water will flash (cavitate) which chokes off flow. l
l
,, LEGEND L.C.= LOCKED CLOSED
. TO EFWP SUCTION H.S.s HAND SWITCH
. E.S.= ENGINE E RED SAFETY FE ATURES I t ACTUATION EF-V5 hMu:. ,
m EF-Y4 hM L.C. - l 1 MS OR ACTUATED ES ~5h- h5+ HS OR
- ES AC TU ATED o o
>< DC i RR-VIOA -
' RR-VIOS i ,- -
III LARGE MESH I! RR-V2A R R-V2 B ' Lt. [ STRAINER L.C . I J i f DISCHARGE DISCHARGE TO RIVE R - f- TO RIVER REACTOR
' BUILDING RR-PIA -
EuERGENCY a RR - PI B COOLING PUMPS
-~~ -
, RIVER WATER (FIG. 4) RIVER WATER SUPPLY TO EFWS- TMi-I
,. ,r.,,-, - - -
l SECTION I-1 REVISION O TMI-1 OPERATIONS PLANT MANUAL l EERENCY FEEDWATER I Table of Effective Pages PAM REVISION ,PAM REVISION PAE REVISION PAE REVISICN 1 0 2 0 3 0 4 0 5 0 6 0 7 0 8 0 9 0 10 0 11 0 12 0
, 13 0 4
14 0 15 0 16 0 17 0 18 0 19 0 ( 20 0
. 21 0 22 0 23 0 24 0 25 0
- Concurrea Autnor ;. .a. 7 % L' + ' C /$ Cate / :-!
Owner / mm Da te / 2 '- F? Cperator Training i A [ Manager, 311-1 .a L llindt#- Date 43 ~ f "D, im b Training Ccordinator, TMI-1 N % . .'. . Cate i li / FY l Approved
- v<
Mana er, Plant Operations (
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l _ .
SECTION 1-1 REVISION O I. REFERENCES R = Reproduce D = Defend or explain given the figure, A. System Gescription
- 1. Emergency Feed Water B. Drawings
- 1. GAI-302-011 Main Steam
- 2. GAI-302-081 Feedwater
- 3. GAI-302-081 Emergency Feecwater
- 4. GAI-302-051 Auxiliary Steam C. Manufacturer's Instruction Manuals
- 1. Worthington Manual on Pumps and Steam Turbines
- 2. Westinghouse Motors
- 0. Procecure
' [ 1. 1106-6 Emergency Feed 2.
- 3. 1202-26A Less of Steam Generatcr Feeo to Beth LTSG's 1202-37 Ccolccwn from Outside The Control Room E. TMI-I FSAR SEction 10.6 - Energency Feecwater Systen F. TMI-I Technical Specifications
- 1. Section 3.5.5 Accident Monitoring Specificaticns
- 2. Section 3.4 Decay heat Remaval, Turnine Cycle
- 3. Section 4.9 E.F.W. Periccic Testing 0539K
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hg1p0h9 N) d' SELTION I-1 (A REVIS1CN U C29 )'t: 111. INTRCOUC, TION The Emergency feedwater system consists of two motor-criven pumps ocnereo frcm redundant Class lE 4160-V buses and cne 100-percent-capacity turbine-driven pump which receives steam frcm the main steam lines or the auxiliary steam line. Both of the mctor-criven pumps and the turbine driven emergency feecwate': pumps will autcmatically start en loss of both main feecwater pumps er less of all four reactor coolant pumps. The motor criven emergency feecwater pumps are automatically loacea en the diesel generator curing less of offsite power with or without simultaneous existence of an ESAS actuation. The three punps are located in the Intermediate Builcing. The turbine-driven pump is physically separated from the motor-criven units. The emergency feecwater pmps take a suction, thrcugh separate lines, frcm the two condensate storage tanks. Tne concenser hotwell can also be used as a suction to the emergency feecwater punps. If the ccncenser hotwell. decreases, the million gallon tank can be lined up to the hotwell. If all the water on site is useo up, river water can be used via the Reactor Building emergency cooling water pumps. Each of the condensate storage tanks has a level incication and two level alarns. Cne alarm is at the technical specification limit for emergency feedwater which set is at 11.5 feet (150,000 gallens) ano the other is { set at approximately 5 feet to alert the coerator that there is 20 minutes of piripable water lef t in the concensate storage tanks at the energency feecwater cesign flow rate. Each emergency feecwater pump is protectec by recirculation lines back to the "6" ccncensate stcrage tank. The three emergency feecwater pumps cischarge into a ccrman heacer f rom which separate 6-in. lines deliver water to each steam generatnr. Each of the 6-in, supply lines contain a flow-limiting venturi ancwn air-operated control valve centro 11ec by ICS. The ICS centrols energency feecwater flow af ter the emergency feecwater purps nave ceen started. IV. SYSTEM FUNCTIONS i The emergency feecwater system celivers water to the steam generatcrs curing less of both main feecwater pumps er 1 css of fcur reacter ccclant pumps for the purpose of (1) remcving cecay heat anc (2) provicing a srcoth reactor coolant transiticn frcm reactor ecciant pung cceraticn into natural circulation. I l l
~ ~
SECTION 1-1 6EV151CN L Suction is shifted to the concenser hotwell when the concensate storage tanks level reaches 1 foot. When ccncenser hotwell level reaches 5 feet, suctirn is shif tec to the millien gallon cemineralizec water storage tank via tne concenser hotwell. River water is not useo unless it is absolutely necessary. The emergency feed pumps then discharge into the respective OTSG via separate lines. Flcw through the lines are centrolled by the 0 -V-30A and 02-V-308 valves. Tne EF-V-30A and E:-V-308 valves are normally controlled autcmatically cy the Integrateo Caltrol System. Emelgency feecwater control valves, 0 -V-30A anc 0 -V308, can al;o be centro 11ec frem tne remote shutcown panels, which are located outsice the centrcl room, if the Control Rcom has to be evacuated. Upon loss of both main feedwater pumps, level will ce automatically controlled at 30" on the OTSG start-up level indica tion. On a loss of all four reactor coolant pumps, the level will be automatically centro 11ec at 50% cn the LTSG operating level. Before the emergency feedwater enters the OTSG it cust pass ( thrcugh the cavitating venturis. Their functicns are listec in Section IV of this cocument. The errergency feedwater enters the OTSG thrcugh the emergency feec ring which is locatec high in the OTSG. The emergency feed ring has seven feec nozzles, but one of the nozzles is blocked to prevent thermal camage to the OTSG Icw~er tubesheet . The b10ckea nozzle cirectec emeIgency feeo into the OTSG inspection lane which crovicea a direct path to the bottom tubesheet. The high location of the feed ring provides a higher thermal center in the OTSG which aids in establishing ratural circulation flow. The feed nczzles each contain a thermal sleeve to minimize the thermal shcck to the nozzles wnen colc energency reecwater is injected into the OTSG. Ob59K
. a SELTION I-1 REVISION O The turbine driven pump is locatec in the Intermeciate Building in a separate compartment on the 295' ficar elevaticn. The turbine driven pump is physically separatec from the two motor criven units. The pump uses a minimum ficw by-pass crifice with a lockec open bypass valve. This recirculation line joins these from the tro meter criven feecwater pumps and is directed to concensate stcrage tank 8. Power to the turbine driven pump is f rom the safety relatec portion of the main steam system or the auxiliary steam system. The two motor criven emergency feecWater pumps are Worthington Mocel 2-1/2 WTF-108, eight (8) stage, horizontal split case, diffuser centrifugal pumps. Each of these pumps have minimum flow by-pass orifices and the fc11cwing cesign cata: Capacity (GPM) . . . . . . . . . . . . . . 460 Minimte ficw (GPN) . ...........84 Total Dynamic Head (ft . ) . . . . . . . . . . 2700 Speed (RPM)
. . . . . . . . . . . . . . . 3570 Tenperature Range ( cF) . . . . . . . . . . 40 - 110 Specific Gravity . . . . . . . . . . . . . 1.0 N3SH requirec ( f t. ) ......... . 16.0 BHP requirec . . . . . . . . . . . . . . . 450
[ Efficiency (1%) . . . . . . . . . . . . . 69.5 Critical Speed (R M) . . . . . . . . . . . 7050 Section Flange (incres) . . . ...... 4 Discharge Flange (inches) . . . . . . . . 2.5 The motor criven feecpumps (2A and 29) are 1ccatec in the Intermeciate Builcing east of the turbine driven pump in a separate compartment on the 295' flocr elevatic.1 All tnree emergency feecwater pump suction lines contain Mack, BT-W 6 inch carben steel strainers of 150# cutt wela ccnstructicn. The emergency feedpump 1A turoine and ptmp tearings, together with the emergency feecpump bearings of pumps 2A and 28 are provicec with a cooling system of recirculated fecewater from the pump discharge to the pump suction. The EFW pump motors are Westinghcuse type CSP, ncri:cntal, squirrel cage, incuction, crip proof witn split sleeve bearings with the follcwing characteristics: 450 h.P. , 36CO R.P.M., 4C00 volt, 3 pnase, 60 cycle. These ptmps have space heaters previcea in the motors to eliminate concensation. 0559K
. 1 . SECTICA I-1 EEVISION O ,
feedwater system controls to previce the native force air
- for valves MS-V-4A/8, MS-V-6, EF-V-3CA/B shoulc the normal plant instrument air corcressors anc the backup histrument air conpressors te lost. Transfer to the twc hour backup air supply is also autcmatic anc nc CPerater action is required.
- c. Failure Mcces The emergency feecwater centrcl valves EF-V-3GA/B will fail open on loss of instrument air anc fail half cpen en loss of control power.
- c. Valve cperation of D:-V-30A ano EF-V-308 B:-V-30A anc Ur-V-308 are located in the motor criven emergency feec pump room.
There ar,e five moces of control en EF-V-30A and D -V-308. These moces are:
- 1. Ncrrally the valves are centrolleo automatically ty the Integrated Centrol System (ICS).
- 2. The valves can De contrc11ec via the ICS by using the 0 -V-30A anc S:-V-3CB Hanc/ Auto station. Tne staticn nust be placed in tne Hanc pcsiticn anc valve position is controllec by the toggle switcn en the Hand / Auto station for 6:-V-30A or 67-V-3CB.
- 3. There is a back-up controller for the valves in the centrol rcom. To use this centro 11er, the respective control switch (censole lett for EF-V-30A and Console center for 8 -V-308) nust be placec in the "back up" position. Valve position is then controlled from the back up centroller.
4 Tne valves may be controlled from the Femote Shutccwn panels which are locateo en the seccrc floor of the control tower. To establish centrol at the remote shutccwn panels there are panal switenes which must te cperatec. Tnese panel switches are locatec as follcws: 07-V-30A - 3rd floor of tre centrol tcwer in the ESAS relay recm near the east wall. EF-%-3CS - 2rc ficor of tre centrcl tcwer 1r. tre remote shutccwn panel rccm cn :ne west wall. . , Obi 9K
SECTION I-1 REVIS1CN O
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i M5-V-13A and MS-y-138 are locatec in the steam criven emergency feed water pump recm. MS-V-13A will open on an "A" emergency feecwater actuation signal to acmit steam to the steam criven emergency feecwater pump turtine. Likewise, MS-V-136 will open en a "B" emergency teecwater actuaticn signal to aomit steam to the steam criven emergency feecwater pump turoine.
- g. Valve Operation of MS-V-10A anc MS-V-108 MS-V-10A anc MS-V-10B are locatec in the steam criven emergency feecwater pump room. These valves are byoasses arcunc MS-V-13A ano 4S-V-13B. They are used to supply steam to the steam criven emergency feeuwater pump turbine when steam pressure gets tco Icw to acequately supply the steam turbine through MS-y-13A anc MS-V-138 alone. MS-V-10A and MS-V-108 are jag contro11ec valves which are operatec from the control room on censole center.
- h. Valve Operation of D -V-8A, EF-V-88, anc EF-V-8C Due to earthquake co1sicerations 0 -V-8A, U -V-6b, anc D:-V-8C are acministratively failec to the cpen pcsition for maximum recirculation.
8 -V-8A and D -V-8C are locatec near their respective motor criven emergency f eedwater ptnp (U:-P-2A ano EF-P-28 ) . OF-V-88 is locatec near the steam criven emergency feecwa ter pump ( EF-P-1) . 4 Cavitatirg Venturi The cavitating venturi's are locatec near the "A" motor criven energency feecwater pump. They are in the northeast ccrner near the ceiling. Figure 3 contains an explanation en how the cavitating venturi wcrks.
. O$59K
0 F SECTION I-1 REVISION O E. To prevent water carry over into the main steam lines, trip all operating emergency feedwater pumps at an OTSG 1evel of 95 percent in the operate range during normal or emergency operation. (This guidance does not acply when performing a flooded nozzle heat-tp or cooldown operation.) F. Follcwing actuation of the 0 W system, an operater must ce sent to the 0 -V-30's area and establish communicaticns with the Centrol Room. This action is necessary to ensure proper operation of the system and enhance the response tine should manual system operation be required. G. The emergency feed pumps will not be used to replace a main feed pu@ for normal operation. H. EFW TtfGTTLING CRITERIA To prevent RCS overcooling due to excessive feed rates, manually control emergency feedwater flow as necessary to maintain OTSG pressure within 100 psig of desired pressure. Monitor RCS cold leg temperatures to ensure feed rate is not causing a significant RCS temperature
.tproncte ransient. Sufficient flow must ce maintained to remove RCS heat anc circulation.
Anytime 0:W ficw is actuated and autcoatically increases steam generatur level to 50% cn the operating range, it can cause significant RCS overcooling. In order to reduce the possibility of thermal cycling of the emergency fee ater nczzles, positiening of the emergency feecwater centrol valves - (D:-v-30A/B) to the fully closed position shcula te avciced curing tne manual control of emergency feeowater flow. Osercoolirg can result when 0 W injects cold water into the OTSG at high flowrates, when trying to cutain tne OTSG 1evel setpoint. When the level increases tco rapicly the inventory accumulation is a colcer heat sink than is required to remove core ' decay heat. Steam pressure drops and the RCS is overccoled. During forced flow, this is quickly reflectec in eclo leg tercerature and RCS pressure. During nat ural circulation the RCS inoications are delayed several minutes due to the sicwer Icep transpcrt tire and are therefore not sultanle parameters to use for feeorate cont rol. Steam generator pressure is tne preferred parameter since it resecnds rapicly to EFW flow changes uncer forced ficw ano natural circulation. Use of this single parameter permits simplified guicelines. Accition of EFW at the maximum rate is not neeced to acnieve stable natural circulation of the PCS, Hcwever, Centinucus ficw is reCuitec tc the OTSG to maintain the nign thermal center in tne LTSG fEF ratursi circulation cf the reactor ecolant water. 1 0559K
SECTION I-1 REVISICN O
- n. 2 Hour Air Bottles - Tnis system is a series of high pressure air bottles wnich are located in the "A" Diesel roon. If the instrument air system cannot supply sufficient air pressure, the 2 nour air bottle will automatically supply the following valves asscciated with the emergency feecwater system:
6 '/-30A 07-V-308 s MS-V-6 MS-V-4A M S-V-48 IX. TECHNICAL SPECIFICATICN A. The reactor coolant system cannot be heated above 250"F with irradiated fuel in the core unless the followirg canponents in the emergency feedwater system are as follows:
- 1. The turbine driven emergency feecwater pump and two half-sired
( motor driven emergency feedwater purps are operable.
- 2. System piping and valves asscciated with the aDove Components are operable.
- 3. Any component cited above may be removed from service for purpose of maintenance for a period not to exceed 48 nours.
If this period is exceedec, the unit will be placea in colo shutdewn within 12 ncurs. 4 As a minimum, one channel of emergency feecwater tiew instrumentation for each ficw path shall be ccerable.
- 9. Erergency Feedwater Pumps Periodic Testing
- 1. Applicability Apolies to the periodic testing of the turbine criven anc twc notar driven emergency feecwater pu,0s.
- 2. Objective To verify that the emergency feecwater pumps anc associatec valves are operable.
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FIGURE-1 EMERGENCY FEEDWATER X 8A CONDENSATE - TANK B NOTWELL d(2A h, s- v v , EMERGENCY 30A e FEEDWATER U CAVITATIE 18 " 2A RIVE R _ PUMP 5 AG VENTUR.I
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SECTION 1-1 REVISION O FIGURE-3 CAVITATING VENTURI
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As water passes through the cavitating venturi it is accelerated as the venturi narrows (point 1). This causes a low pressure area to be developed at point 2. When the pressure at point 2 reaches the vaporization pressure of the water, the water will flash (cavitate) which chokes off flow. e o
FI G U R E-5 EF-V3O A/B CONTROL AIR SOURCES i INSTRUMENT AIR l AIR TO CONTROL THE CONVERTER BACKUP AIR % FLOW OF REPOSITIONING AIR ' 2 HOUR BOTTLE AIR , s . IN5TRUMENT AIR y 0AWAM
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i TABLE 1 ilME FOR EMERGENCY FEEDWATER PUMPS TO REACH FULL SPEED START TlHE TO FULL START TlHE TO FULL EVENT SIGNAL EFPI SPEED EFPI SIGNAL EFP2 SPEED EFP2 LOSS OF FW OR LOSS OF RCP IMMEDIATE 18 Sec. 5 Sec. 15 Sec. LOSS OF FW OR IMMEDIATE 18 Sec. 15 Sec. 25 Sec. LOSS OF REP AND LOSS OF OFFSITE POWER LOSS OF FW '
; OR IMMEDIATE 18 Sec. 20 Sec. 30 Sec. !
LOSS OF RCP AND ESAS LOSS OF FW OR LOSS OF RCP iMMEDIATE 18 Sec. 30 Sec. 40 Sec. Al4D ESAS AtJD LOSS OF OFFSITE POWER SG ra 1 2* oi 6
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CPU NUCLEAR ORGANIZATION PLAN This Plan is provided to describe the responsibility, assignments and principal activities for CPU Nuclear at the Division, Department and Section levels. The CPUN ' organization structure has betn specifically designed to enable the nuclear plant operating Directors to concentrate their ef forts on operating the plants safely with administrative and technical support provided by functional divisions. These functional which enhance _ divisions provide not only expertise but also important checks and balances safe operations. -
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It is the responsibility of each Division Director Manager and Supervisor to be faellfar witi.,this Plan and to cooperate both inter and intra-divisions 11y to assure an the Plan is effectively implemented., Each member of management is also to review that iscuss the Plan with their employees to assure th i e r understanding - H ' Resoyrce's is responsible to conduct a formal review of the Plan annuallh uman No changes may be made to the organization depicted herein, the responsibilities set forth,dent, Presi, nor to the titles of the yarious positions, except by the Office g of the Organization Plan Revisions".,in accordance with the provisions of 1000-ADM-2003.01 " Processin Prior to issuing any changes,'the' proposed revisions
'sha'111be reviewed by the Director - Licensing and Regulatory Affairs to assure the
~
. giroposed reyisio3 ,does,,not conflict with any of the plants' licensing'r' equirements.
Division' Directors,q e responsible to ensure that all documents'which set forth or re desEf twi ~gubordinate organization . structures 'are also ik con'fofmanhe wl'th[the plant , licen sin. g3 re.{)uirement s. s . . .
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00C /NAL. SIGsisD By PkCLk2K' 2 fff s APPROVED ' DATE o CONTROLIID DOPY kO'. M d 1/86 x A ___---- - C---_-------- - n.
O O O EFU NACLEAR CGIFORATION BOARD OF DIECIORS GPU MACLEAR 1 COIPORATION l PESIENT i i CHIEF EEQlilVE f 0FFICER j EEEUTIv( VICE PESIDENT I CHAIRNAN CORB i l l l l , DIKCIOR DIECTOR DIKCTOR OYSTER CKEK TN1-1 TNI-2 I I I I I I I I DIKCIOR DIKCTOR DI KCTOR DIECTOR DIKCIDR DI ECTOR C00fiROLLER TECHNICAL MACLEAR ADNINISTRAT10N CDPMINICATIONS RAD. & ENVIRON. NAINT/CONSTR. & FUICIIONS ASSIRAEE CONTRE S FACILITIES I j 1/86 I l 1 I -
r, ' i i
~ .
i FMCTIONS OF OFFICE OF PREFIM NT l i 1 i
; Provide a full-time dedicated management for the purpose of conducting all nuclear j activities of the system safely and ef fectively.
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CENERAL OFFICE REVIEW BOARDS FUNCTIONS AND RESPONSIBILITIES The primary responsibility of the General Office Review Board is to consider potentially , significant nuclear and radiation safety matters and related management aspects of those matters at each plant and to advise the Of fice of the President of them and make recommendations for mitigating the situations. A secondary responsibility is to consider potentially significant industrial safety matters. The GORB reports to and takes general direction from the Of fice of the President, CPU Nuclear Corporation. However, the CORB or I any individual menber thereof may, at any time, make oral or written comments to the Board of Directors of CPUN and its parent organization concerning matters considered to be 4 within the CORB's area or responsibility i l j i 1/86 CORB Pg. 1
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CPU NUCLEAR OYSTER CREEK DIVISION SlSenRY OF RESPONSIBILITIES operate the Oyster Creek plant in a safe, environmentally sound, reliable and efficient manner in accordance with corporate policies and all applicable laws, regulations, licenses and technical requirements The Division Director is the. senior CPUN representative at Oyster Creek and as such assures consistent implementation of policies and procedures at the plant and at CPUN off site facilities in the Oyster Creek area MAIOR FUNCTIONS Operate the plant i Provide and maintain qualified staff Establish cardinal dates for plaat evolutions and outages Control the scope of work in the pisnt i Define and establish priorities for preventive and corrective maintenance and refurbishment work needed to ensure good plant material condition
- Establish and maintain plans and schedules, policies, procedures, standards and practices for the Division i
l Develop, gain approval, and operate within approved annual budget, annual operating l plan, and the multi year strategic plan j Establish day-to-day priorities for plant support Develop and maintain effective consultation with other Divisions to help assure j efticient functioning of CPU Nuclear i 1/86 i DC i Pg. 1 i
OTSTER C E EK a EFICE OF INE PRESIDENT If 00 l DI KCTOR , OYSTER CEEK 4 wruir
- DIK CTOR 7rnn 7______,
_ _ _ _ _ _ _J SArEir KviEw l I MANAER l ! l_ _ _2990_ _ _I
- INGR. PLANT ADN./l
-------l M;R. !PECIAL l l PRRECTS l 4
1 _. _. 100_0 _ _I I I I I NANAE R PLANT PLANT NANAER PtANS & (PERATIONS ENGlKERING PLANT PHOGHAMS DIKCIOR DIKCTOR MATERIEL { 2020 2100 ??nn 2300
*0utted line indacates Staff Position 1/M
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1 FIAMS AND PROGRAMS DEPARTMENT SIRGIARY OF RESPONSIRILITIES I
, Provide administrative support to the Director and Deputy Director Oyster Creek (Of fice of the Director - 0.C.), monitor the effectiveness of all plant programs and provide coordination between the plant and support divisions during an operating cycle l Assure coordination between the plant and support divisions for all outages and construction projects l
MMOR FUNCTIONS Develop site and division policies and administrative procedures Provide coordination and establish day-to-day priorities for plant support during an operating cycle Assure coordination between plant and support divisions for all outages and construction projects Establish cardinal dates for plant evolutions and outages Assist in development of integrated plans and schedules for all outages Assist in development of maintenance and modification workscopes, including budgetary ! requirements - l Allocate funding to support divisions for plant sponsored projects ! Act as liaison for designated interdivisional projects and with support divisions, system companies, external consultants and industry groups 1 4 Coordinate plant division Goals and Objectives Program l 1 Prepare inputs for Board of Directors and other corporate-level reports 1 l j 1/86 oC ! Pg. 3
e, - I DIKCIGR DYSTER LEEK i .- ....___
! DEPU TY DI ECTOR 7f nn l
MANAER PtANS & PROGRAMS 2020
. Develop Site and Diviolon Policies
, and Administrative Procedures t
. Provide Coordination and Establish Day-To-Day Priorities for Plant Support During An Operating Cycle
.Aesus,e Coordination Between Plant And Support Divisione For All Outages And Construction Projects
. Establish Cardinal Dates for Plant
- Evolutions And Outagne
.Aselet In Development of Integrated e
Plans And Schedules For All Outages
.Aselet In Development Of Maintenance j
And Modification Workecopes, Incit: ding - l Budgetary Requirements
. Allocate Funding To Support Divisions j For Plant Sponsored Projects
.Act As Lietoon for Designated Inter-Diviolonel Projects And with Support Diviolone, System Companies, External I
consultants And Industry Groupe
.Coordinato Plant Diviolon Coals And (bjectives Prograis
. Prepare Inputs for Board of Directors j And Other Corporate-Level Reporte l 1/86 0C
- Pg. 4
PLANT OPERATIONS DEPARTMENT SthetARY OF RESPONSIBILITIES Conduct plant operations, radwaste and chemistry activities at Oyster Creek in a safe, reliable and ef ficient manner consistent with corporate requirements and in compliance with all applicable laws, licenses, regulatory / technical requirements and station procedures MAJOR FUNCTIONS
- Conduct plant operations activities to provide maximum capability in a manner l
consistent with license, regulatory and corporate requirements Operate Radioactive Waste Facilities, Augment Off-Cas (AOG) building and station boilers l Administer the Radioactive Material Handling and Shipping Programs Conduct the plant chemistry program i Coordinate with Maintenance, Construction & Facilities, Technical Support, Administration, Radiological & Environmental Controls and Nuclear Assurance to assure proper support, control and prioritization of activities with respect to plant operat ions Provide guidance and align plant systems to support plant evolutions and outages i Provide, train and maintain qualified staff Monitor performance and provide recommendations for applicable training programs l 9 1/86 OC Pg. 5 l
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PLANT ENGINEERING DEPARTIGINT SIDGIARY OF RESPONSIBILITIES Provide engineering and technical services in support of day-to-day plant operations and maintenance, implement fire protection program and provide technical assistance to the chemistry program to support plant operation in a sate, reliable and efficicnt manner and in accordance with corporate policies and all applicable laws, regulations, licenses and technical requirements MAJOR FUNCTIONS Provide day-to-day engineering and technical support to plant operations and maintenance Prepare or assist in preparation and review of plant operations, emergency, ! maintenance, alarm and surveillance procedures Conduct operations experience assessment and problem investigations Prepare spare parts specifications and assist in procurement Develop, implement and ensure compliance with the fire protection program Provide technical assistance to the chemistry program ) Provide day-to-day incore fuel management , Coord inate with and request technical support , as needed, from Technical Functions i Division j Initiate investigations, responses and corrective actions, as required by regulatory I correspondence i Provide design packages to support plant modifications, as authorized by and in i accordance with corporate and Technical Functions procedures I, j Specify the In-Service Test (IST) and Master Surveillance Requirements } Provide emergency operational support 4 1/86 oc Pa. 7
DIKCIOR OY:sIER CKEK DEPUTY
, DI KCIOR tr nn l PLANT ENGIEERING l DIK CTOR 2 : 110 . Major Site Projects
- ESSF l~ 5 .~ PLANI-~~l* - LLRW
_ _ -. _ _ _ _l EEIKERING l - EPRI l PROXCTS I .Pesliainary Engineering Design Asview l_ _ 220_0 _ _l . Operability, Maintainability, Constructability Review , .Uutage Planning & Sg port i l l ER. M41NIEfeMCE ER. (PERAI10NS ER. SAPP (uti ENGIKE RING EEIEERING EMIKERIE (ELECIRICAL ) (ECHANICAL) 2* M) 2240 2250
. Electric PWR And . Core Engineering .Machenical Plant En-
, Distr. Engineering - . Operations Engineering gineering j Plant .Chee/Redweste-Environ- . Space Parte Engineering
. Post Maintenance Test sental Systems Progreen . fire Protection & Safety
. Plant Contact (If BA's) . Plant Contact (if BA's) Progrees
. Project Engineering . Project Engineering . Plant Contact (IF BA's)
(PED BA's) (PED BA's) . Project Engineering
.04M Problem Resolutions .operatione Probles Re- (PED BA's)
. Procedure Preparation solution .0AM Problem Resolutions
& Contro! . Procedure Preparation & .Procedura Properation &
. Test Acceptance Group Control Control
. Safety Review Manager .iest Acceptance Group . Primary Maintenance Support Primary Operatione Interface (Mechanical)
.Tranesent Analysis Support Interface
. Primary M.sintenance I
Interface (flectrical)
' Dotted late indacates Staff Position 1/86 Oc i
,s - -
PLANT MATERIEL DEPARTM NT l SUtet&RY OF RESPONSIBILITIES
- Upgrade and maintain the material condition of the plant consistent with safe, reliable
- operations and in accordance with corporate policies and all applicable laws,
- regula tions , license and technical requirements MAJOR FUNCTIONS Identify materiel deficiencies, establish priorities and assign responsibilities for their timely resolution Administer Preventive Maintenance programs to support operation of the plant consistent with license, regulatory and corporate requirements i Administer the conduct of plant surveillance programs consistent with applicable j regulations and sound engineering practice i Administer a Station Services support program to complement and enhance the performance i of plant operational objectives Conduct activities of Plant Fire Protection Programa i
l Administer the Respirator Maintenance, Cleaning and Issue Program in support of plant operations, consistent with Plant and regulatory requirements i Administer special programs, i.e. NPRDS, NHL Boiler and Machinery Inspections, NOMIS l and Long-Range Planning Develop and administer a Predictive Maintenance Program, i.e. equipment failure j trending, vibration and lubricating oil analysis i Function as primary plant contact for disposition of all MNCRs, QDRs, LAIs relative to materiel deficiencies in existing plant equipment i i Conduct decontamination activities to minimize contaminated areas of the plant - l 1/86 i OC , j Pg. 9
- i
.i
O PIANT MATERIEL DEPARTMNT - (continued) Provide plant evaluation and approval of maintenance work activities. Review completed work activities for equipment history and reportability requirements Provide input for development of budget activities which will enhance plant generation reliability Develop procedural control and Preventive Maintenance Check Sheets in support of corporate and regulatory Environmental Qualification (EQ) requirements 1/86 oc Pg. 10
A ' i DIK CIOR OYSTER CREEK 2f 00 MNAER PLANT MIERIEL 2'no l I I l ] M CHANICAL ELECIRILAL/IAC PEVENIIVE STAl10M E RVICE SIPERVISOR MAIERIEL MAMER MIERIEL MANAER MAINTENAEE PRG; RAM MANAER IECHNICAL S8PPORY MANAER 2310 2310 2320 2330 2300/2340
.Revioen/ Approve "Short . Review / Approve "Short . Review / Approve "Short . Administer The Protective . Review / Approve "Short l Forme"-Corrective Forms"-Corrective Forme"-Corrective Clothing (PC) Program Forme"-Corrective Maintenance Requeste Maintenance Requeste Maintenance Requeste . Administer Plant Labeling Prog. Maintenance Requeste i
. Identify Mechanical . Identify Electrical /I&C . Administer Preventive Main- . Conduct Plant Decon Activities i
Materiel Deficiencies Deficiencies tenance (PM) Program Program . Manage Plant Reepirator
. Evaluate / Initiate . Evaluate / Initiate . Administer Tech Spec .Meintain Han==areeping Within Maintenance Program Corrective Actione Corrective Actione Sury. Program EA's . Administer Site Nomis
. Develop Equipment . Develop Equipment .Dowelop, Revise, Review . Support Redweete Shipping Program l Trending Program Trending Program All (PM) Sheete Program . Coordinate " ,_ -
) . Develop Vibration . Administer WRDS Fall- . Develop, Revise, Review . Support Plant ACRA Program & Track The followings
- Analyste Program ute Reporting Program All (PM) Procedures .Sipport Plant Reapirator -Regulatory " . - -
- / LAl's
! .Adminleter NK Boller . Support Long-Range Plan- . Administer the Snubber Maintenance Activition (Licensing Action items) i and Machinery Inapection ning (LW) Program Surw. Program . Conduct Plant Crane E5erator -leCR'a/QDR's l Progran . Administer Special Pro- . Direct Conduct of Plant Program -Goals & Objectivee
; .Sipport Long-Range Plan- grene Sapporting Plant Fire Protection Program .therete On-Site Laundry -Completed M&C Short Forme j ning (LW) Program Upgrade . Support Development /In- . Support Special Projects -Personnel Training & Per-i . Administer the Heat . Maintain Equipment plementation of SIMS Pro . .Adminleter Plant Rerurbleh- formance j Exchange (HX) Monitoring History Recorde gran ment Program -Procedure Reviews /Re-l Program .Sepport & Implement Equip. visione l . Administer Special Pro- (PM) Program -IW O Findinge
} grane Si , porting Plant .Sipport Long-Range Plan- . Administer Special Programe l Upgrade ning (LW) Program f . Maintain Equipment . Administer Special Programs i History Hecorde 1/86 j OC j Pg. 11 4 I e
,-~ ~ .
SAFETY REVIEW DEPART M NT 844etARY OF RESPollSIBILITIES Implement the Safety Review and Approval process for the Oyster Creek Division in accordance with Corporate Policies and Procedures. Technical Specifications and Federal Regulations
- Perform the Procedure Coordinator function for the Oyster Creek Division RIAJOR PUllCTIOIBS Assign qualified Responsible Technical Reviewers (RTR) and Independent Safety Reviewers-l' (ISR)
Assure all required reviews of placs, policies and procedures are performed prior to Division Director approval J Maintain records of Safety Review process , ! Schedule and maintain records of periodic procedure reviews l Coordinate review of other divisions' plans, policies and procedures by Oyster Creek ' Division for Division Director's concurrence 1 l i 4 1/86 oC
- Pg. 12 .
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GPU NUCLEAR THREE MILE ISLAND UNIT 1 DIVISION l SUNNARY OF RESPONSIBILITIES Operate the TMI-l plant in a safe, environmentally sound, reliable and ef ficient manner in accordance with corporate policies and all applicable laws, regulations, licenses and technical requi rements The Division Director is the senior GPUN representative at the TMI site and as such assures consistent implementation of policies and procedures at the plant and at GPUN ' off-site facilities in the TMI area. The Division Director - TMI'-1 can transfer this responsibility, to the Director - TMI-2, with his agreement, for specific matters or time periods MAJOR FUNCTIONS Operate the plant Provide and maintain qualified staff Establish cardinal dates for plant evolutions and outages 1 Control the scope of work in the plant l Define and establish priorities for the preventive and corrective maintenance and refurbishment work needed to ensure good plant materiel condition Establish and maintain plans and schedules, policies, procedures, standards and i practices for the Division i j Develop, gain approval, and operate within approved annual budget, annual operating plan, and the multi year strategic plan Establish day to day priorities for plant support l l Develop and maintain ef fective consultation and advice with other Divisions to help assure efficient functioning of GPU Nuclear i 1/86 l TML-1 Pg. I
g, . . TMI-1 DIVISION 0FFICE OF THE PE SIDENT 1 DIECTOR TMI-1 i X 00 l l l 1 I i mNAGER PL ANT TS. & MINT. PLANT EE. ER. PROGRAMS ADMINISTRATION DIR. TMI-1 DIR. TMI-l & CONTRILS TMI-l TMI-1 1100 3200 3300 3MMI l l 1 1 1/86 TMI-l Pg. 2
i . - g . . PLANT ADMINISTRATION DEPARTHENT SIRetARY OF RESPONSIBILITIES l Provide administrative support to the Director, TML-1 MAJOR FUNCTIONS i Coordinate administrative activities between the TM1-1 Division and the Support Divisions in the areas of Financial /Information Services, Materials / Management, Human Resources, Security, Facilities and Industrial Safety & Health Day-to-day coordination with human resources, security and facilities activities - l Assist the Director, TMI-l in staff planning, correspondence and scheduling I i Prepare inputs for Board of Directors and other corporate level reports . I Coordinate various activities and administration requirements of outside j evaluators / inspectors Coordinate divisional objectives and goals program Administer division wage and salary program Develop / coordinate responses for assigned special evaluations such as INPO Act as liaison for designated inter-divisional projects and act as liaison with assigned support divisions, system companies, external consultants and industry groups 4 l I a 1/86 TMI-l l Pg. 3
I i DIKCTOR l TMI-1 mrn ( r 1 l I MANAER PLANT ADMINISTRATION 3100 + I . Coordinate Site Activities
. Personnel Nage and Salary Progrees
. Coordination of Reporte
.Ibjectives and Goals Progree -
! . Coordination of Special Evente I i ) i I i I i 1 1/86 iMI-1 Pg. 4
n . . OPERATIONS AND MAINTENANCE DEPARTMElfr l SUlelARY OF RESPONSIBILITIES Conduct plant operations, radwaste, chemistry and maintenance activities at Three Nile Island Unit 1 in a safe, reliable and efficient manner consistent with corporate
; requirements and in compliance with all applicable laws, regulatory and technical requirements; included is the efficient implementation of the corrective and preventive maintenance programs MAJOR FUNCTIONS j Conduct plant operations and maintenance activities to provide maximum capability in a j manner consistent with license, regulatory and corporate requirements Direct the implementation of a preventive and corrective maintenance program including the prioritization to assure the plant is maintained in a safe, efficient and reliable manne r Direct the operation of the Radioactive Waste facility, including the conduct of the j radioactive material handling and shipment programa , Develop, implement and ensure compliance with the plant chemistry program Coordinate with Maintenance, Construction & Facilities, Technical Functions, Adminis t rat ion, Radiological and Environmental Controls and Nuclear Assurance to assure proper support and control of activities with respect to plant operations and maintenance are achieved I .
Coordinate the plant procedure program j Provide a Plant Neview Group that meets all regulatory and company requirements i Provide plant input to applicable training programs i 1/86 l TMI-1 Pg. 5
g . .
; DIRECTOR ---------
3 TMl-1 l wn l l l (PERAI!UNS AM) l MAINIENAN'E l DIRECTOR IMI-1 l )l 32fC l . Plant Review Group Chairman j . Safety Review MNAER SAFETY . Tech Spec Reporting Requiremonta j HEVIEW .tER Coordination 3200 . Procedure Progree Control I __ _ __ _. ._ _ _l TRAINING l l COORDINATOR l i l_ _ 12" _ _ I l ~ 5)PfAVTt0K - l
--_---._.__-.l STATION l l (PERATIONS III l l_ -. L200._ __ _l l l l
) MNAGER PLANI MANAGER PLANI PLANT CE MISIRV l (PERATIONS M41NifNAfCE MANAER ! IMI-I IMI-1 TMt-1 3210 3220 3230
. Day-To-Day Opera- .Uperate Plant Equip- . Administer the PM .Perfore PM Taeke . Ensure Compliance . Development and Imple-tions of IMI-1 ment & Ensure Compli- and CM Prograee . Shift Maintenance with Water Chemistry mentation of Chemistry
.TMI-1 Radmaste ance with St' ate & . Planning, Scheduling . Plant Cleanliness Tectnical Spece Progree Processing & Ship- Federal Regulations of Maintenance Acti . Administration of . Support Plant the/ . Prepare Purchese Re-ment .Uperate IWS/lWIS vities Generation Maintenance Maintenance on Re- quieltione
. Coordinate opa/ . Technical Specafi- . Technical Specifi- System lated Items . Coordination of Cheels-Maint/Constr/ Rad- cations Surveillance catione Surveillance . Administration of WADS .Trond Analytical try Requirements &
Con Activittee on . operate & Maintain .Perfore CM and Data Conditions with Tech Shift the Sewage Ireat- Repair Work th All . Procedure Propera- functions & Plant
. Primary / Secondary ment Plant Plant Systems tion and Implementa- Engineering Plant Operations tion 1/86 THI-1 Pg. 6
, . o PIANT EEINEERIE DEPARTMENT SLRetARY OF RESPONSIBILITIES Provide engineering and technical services in support ot day-to-day plant operations and maintenance, implement fire protection program and provide technical assistance to l'
the chemistry program to support plant operation in a safe, reliable and efficient manner and in accordance with corporate policies and all applicable laws, regulations, l, licenses and technical requirements ! MAJOR FUNCTIONS Provide day-to-day engineering and technical support to plant operations and maintenance i Prepare or assist in preparation and review of plant operations, emergency, i maintenance, alarm and surveillance procedures Conduct operations experience assessment and problem investigations Prepare spare parts specifications and assist in procurement Develop, implement and ensure compliance with the fire protection program l Provide technical assistance to the chemistry program l Provide day-to-day incore fuel management Coordinate with and request technical support, as needed, from Technical Functions l Division j Initiate investigations, responses and corrective actions, as required by regulatory 1 correspondence l l Provide design packages to support plant modifications as authorized by and in j accordance with corporate and Technical Functions' procedures I I I l 1/86 [ THI-1 l Pg. 7 I
i DIECTOR IMI-1 i 3000 l PtANI Ela;1 EERIE DIRECTOR i IME-1 3?00 l I I I DeueMIR BWUt u R LEAD pHCLEAR K NIER l PLANT EElWERIE PLANT CE.lEERIE EEIKER CE MIST iMI-1 IMI-I l 3E0 3300 3320 3MO
! . Provide En- . Provide Plant En- .Provice En- . Provide Plant En- . Provide Day-To- belear Fuels . Purchase Re-gineering Support gineering Input gineering Support gineering Input Day In Core Fuel Group quiettion Re- ]
1 To Plant Opera- to Tech functione la Plant thera- to Tech Functions Ar+; - .t . Tech Sgport view & Prope-tions/ Maintenance . Evaluate & Coordin- tions/Meintenance . Evaluate & Coordin- . Review & Imple- For Outages ration I Departmenta ate laplementation Departmente ate Implementation ment Long Tore . Initiate Investi- . Provide Input
. Technical Support of Technical Recom- . Technical Support of Technical Recom- Fuel ". rc - .t gotions & Correct- to Training i For Outages mandations For Outages mandatione .Propere & Support ive Actione In Re- Dept., As Re-
. Initiate Investi- . Provide Input to . initiate Investi- . Provide Input To Refueling /Physico sponse To Regula- quired i gations & Correc- Training Dept., As gotions & Correc- Training Dept., As Testing Procedures tory Directives & .Sgport PRG tive Actions In Required Live Actions In Required . Provide Aseletance For Properation of Activities Reeponse to Regula . Develop & Coordin- Reeponse To Regula- .Sgport P K Acti- To (5eratione on Licensee Event Re- . Tech Aeoiet-tory Directives & ate Plant IST Program tory Directives & vities Core Operation porte, As Required ance To Chem for Preparation of .S+ port P E Activities For Properation of . Security a r - .SNM Accounting . Provide Input To Program j Licensee Event Re- . Implement fire Pro- Licensee Event Re- nication Projects .Special Core Training Dept., As . Procedure
! porte, As Required taction Plan porte, As Required To Meet Physical Testing Required Properation & j .Proce&re Prepara- . Provide Operationa/ . Procedure Prepare- Security Plans & . Provide Core . Support P E Acti- Review , i tion & Neview Maintenance Fire tion & Review 10CFR73.M Require- hanagement Liaison vities . Provide Chem-l . Purchase Requisi- Protection Assist- . Purchase Requiel- monta Between Plant & 1stry Liaison ! tion Review & ance Lion Review & Between The Preparation . Prepare & Review Preparation Plant & Tech Fire Protectaon functions / Proceduree GPUSC Lab
. Perform Fire System Surveillance 1/86
! THI-I Pg. 8
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i i PaMmann AND CONTROI.S DEPARTISNT 4 State &RY OF RESPOIISIBILITIES i Provide services to the Director TMI-1 in the' areas of planning for overall Plant l activities MA.JOR FUttCT100tS TMI-1 representative on the long Range Planning Croup Assist the TMI-I Director to establish plant milestone dates and prerequisites for major activities, for use by support Divisions in their planning processes Assist the ohm Director and his staff with all aspects of outage coordination, to include responsibilities for prerequisite listings, overall planning and tracking I status for management re porting 1 Coordinate, develop and maintain major plant evolution sequences to include i surveillance test procedures and job ticket retests. Also, interface with support l Divisions who's scheduling systems depend on key dates extracted from the above 4 sequences l
; Develop detailed schedules and analysis for plant Division departments, as requested I Coordination and monitoring of work assigned to MCF l
Monitors major PM, surveillance and EQ requirements to ensure coordination with overall 1 plant schedule and key events I i Coordinate the "no name" outage work list with the plant and other affected divisions f I i r I t i i I l i 1/86 ,
! TMI-1 , Pg. 9
i e i i DIKCTOR IME-1 X 00 l HMnER P90 gam 6 & CONTRES i m00
.Long Range Planning
. Coordination of fuork Assignment I to E F l . Monitor Major PM's And Surveillance For Schedule Conflicte
[ . Coordinate "No Name" Outege Work List 3 l With Other Diviolone I i l i 4 i 1/86 IME-1 Pg. 10
.I
GPU IWC12Ag CORPORATICN 7tIREE M112 ISLAND UNIT 2 DIVISION SthetARY OF RESPONSIBILITIES operate and conduct decontamination and recovery operations of TN1-2 in a safe, environmentally sound, reliable and ef ficient mas:ner in accordance with corporate policies and all applicable laws, regulations, licenses and technical requirements. This includes design and construction of required facilities IIMOR FU41CTI0 TIS Provide and maintain a qualified staff Direct and control the plant decontamination and recovery programs, including the design and construction of required facilities Establish cardinal dates for plant evolution, decontamination and recovery activities Operate and maintain all systems and equipment required for decontamination and recovery of systems Direct all licensing matters related to TMI-2 Provide safety review of significant procedures, plans and design changes independent of Engineering and Operations Groups Provide risk assessment of all major TML-2 activities Control the scope of work in the plant Establish day-to-day priorities for plant support Define and establish priorities for the preventive and corrective maintenance and refurbishment work needed to ensure needed material condition Establish and maintain plans and schedules, policies, procedures, standards and practices for the Division Develop, gain approval, and operate within approved annual budget, annual operating plan, and the multi year strategic plan Develop and maintain effective consultation and advice with other Divisions to help ensure ef ticient functioning of CPU Nuclear 1/86 THI-2
. =
l TMI-2 DIVISION 1 i l I WFICE OF THE
- PESIKNI 1
I DI KCTOR TMI-2 4 l
, DEPU TY i
DI KCIOR f Anr n i i 1 i 1- EEF 7
~ ~ ~ ~ ~ ~ ~l ADMIN!STRATIONI
] I MANAER 1 l_ _ .19119._ I i I I I I I i meus a sia MAM un utmann zu.rimutu PROGRAM WERA110NS KCGfERY LICENSING & PLAteilNG CONINULS DIKCIOR Ph0GaANS DUCLEAR SAFEIY & ANALYSIS anno awin a nn aano 4500 l l i l l l i i
- 1/86
' IMI-2 Pg. 2 l
m PL& art ADMINISTRATION DEPARTMENT q S49et&RY OF RESPONSIBILITIES i Provide administrative support to the Director, TML-2 j BIAJOR FU40CTIONS i l Coordinate administrative activities between the TMI-2 Division and the Support Divisions in the areas of Information Services, Materials / Management, Human Resources, Security, Facilities and Industrial Safety & Health Day-to-day coordination with human resources, security and facilities activities, as required Assist the Director, TMI-2 in staff planning, correspondence and scheduling Coordinate inputs for TMI-2 Division, Board of Directors and other corporate level meetings, as required ! Coordinate various activities and administration requirements of outside
- organizations / indust ry groups, as required
- Act as liaison for designated inter-divisional projects and act as liaison with I
assigned support divisions, system companies, external consultants and industry groups, as required 1 l Coordinate division objectives and goals program l Administer division wage and salary program Coordinate divisional employee meeting attendance / travel program and interface with corporate management for approvals, as appropriate l I i I 1/86 i TMI-2 Pg. 3
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Pe0Gaats CoerruoLS DEPARTMkMT , sires &RY OF RESPONSIBILITIES Provide Program Controls support to the Office of the Director, TML-2 HMOR FUNCTIONS Manage Program Plans and Summary Schedules Coordinate Program Plan Estimates, Budgets and Costs a Prepare and issue summary Program Plan Management Reports internal / external Provide Program Controls Policies / Methods / Procedures and administer their execution Provide administrative support to the Of fice of the Director, TML-2 Develop and maintain TML-2 Administrative Procedures Administratively control modification and work related documents s 1/86 TML-2 Pg. 5
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1 i SITE OPERATIONS DEPARTMENT I
; SIMaERY OF RESPONSIBILITIES i
Conduct plant operations, maintenance, engineering, waste management, defueling t operations and fuel shipping in a safe, reliable and efficient manner consistent with corporate requirements and in compliance with all applicable laws, licenses, regulatory ,I and technical requirements i
, MMOR FUNCTIONS
,i j Operate and maintain the plant in a safe, reliable and efficient manner i Direct the operation of radioactive waste facilities, including the conduct of the Radioactive Material On-Site Movement and Shipment programs ' Direct defueling operations and fuel shipping in a safe manner consistent with ALARA requirements j i Provide various plant support services to other TMI-2 departments, such as respirators, laundry, crane operators, tool rooms, weld rod issuance, etc 1 l I . ) 1/86 THI-2 Pg. 7 l
TMI-2 DIVISION I DIRECTOR IMI-2 4t ua l' l~ "MEdR ~l SilE (FERATIONS _ _ _ _ .,,j DEFUELING l . Direct a Safe and j DINECIOR l l Expeditious Defueling i
'* l_ .,. .g0__ _l Program I i
] MMeAE R MMcAER MAM ER MMe ER f PLANT PLANI WASTE PLANT j (PERATIONS MAINTENAEE MMeAGEENT ENGlKERING j 4210 4220 4230 4240
. Direct Safe and Stable . Direct the Corrective, . Direct Operations of . Direct and Implement all Operation of the Plant Preventive and Recovery Solid Waste Processing Plant Engineering Support I . Provide Plant operational Operation Maintenance Systems Services for Operatione I
Communications wath NNC Activittee . Provide Proper Packaging & Maintenance i . Direct Operation of . Provide Training Programe of Radioactive Meterial .Specify Required Plant Eheels-l Cheetatry Laboratory and Personnel Programe . Direct Radioactive try and Radiochemistry
. Direct Operations of to Ensure Competent Shift Material Movement and Services Liquid heeta Processing Coverage Shipping Program . Provide and Direct Fire Pro-
- Systems . Implement Radiologacel . Provide Interface with taction Engineering and
. Implement Radiological Work Cantrol Checklista ME and DOI on Redenote Capability for unit 2 Work Control Checklista in the Planning, Propera- Shipmente . Coordinate and Identify in the Planning, Prepara- tion and leptementation .leplement a shate Sample Analysis Prograse tion and Implementation of Work in Rtr required Volues Reduction Progree Including Contractors and i
of Work in Hke Required Areas . Direct @ ration of Re- On-Site Contractor recilities Areae .
.Meantain Control of and covery Support facilities .Ameure Technical Matey of
- . Prepare Final Operating, Implement Various Admin- (Laundry and Reepirator) Systems and R
- overy Sapport j Procedures intrative Control Pro- Surveillance Program grame for Calibrated In- . Interface with Site Engineering struments & Tools, Welding on Non-Recovery Systems Engineering and Rigging and Handling, Probleme etc. . Monitor and Control Plant Conditione i
1/86
' IMI-2 l
_ _ _ _ _______ R h 0 ______ ___ __
m RECOVERY PROCRAMS DEPARTMENT SimetARY OF RESPONSIBILITIES Provide engineering and field operations support necessary for decontamination of the i TMI-2 facility and fuel removal consistent with approved Technical Plans. This includes design and construction of new facilities and modification of existing facilities required for recovery. Activities shall be conducted in a safe, reliable and efficient manner and in compliance with all applicable laws, licenses, and regulatory and technical requirements MAIOR FUNCTIONS Direct and control TMI-2 recovery through. the decontamination and cleanup of buildings and spa-es and the construction of required support facilities Direct and control the activities required to provide the ability to remove the damaged core from the reactor including the construction of required support facilities Provide technical support services to Site Operations and other TMI-2 departments, as requested Direct engineering services, including configuration control or recovery systems, structures and components, in support of Site Operations Direct the maintenance of the master recovery cost and schedule and attendant performance measurement systems for the Recovery Programs Department scope of work Maintain and direct operation of recovery systems not turned over to Site Operations Coordinate and conduct containment entries necessary for recovery support of defueling and decontamination operations l l l I/86 TMI-2 Pg. 9
TMI-2 DIVIS10N
- DINECIOR TMI-2
, uva i
a Mus E A
- KCOWERY
- -- - - - - PR(ER
-.A.M.S_
DEPuiY MANAGER 4300 Il l'1E'% TbpWATTeGi~l . Coordinate and Conduct I 1, ______l ENINY GR(UP l Containment Entries Necessary 8 SIPERWISOR l for Recovery Support of De-l_ _ am_0 _ _ _t ra ling & Decentamination Ope. l~ TAE LE5R' ~l . Evaluate and Coordinate _ _ _ _ _ _jKACTOR DISASEMILYl Activities within Assigned E4D l A KFUELING l Taeks and Provide Department Level j l_ _ 4)o_0 _ _ _l Programmatic and Technical Direction
~
f iASK L 5 0 d ~ l . Evaluate and Coordinate ______l DEIDELING l Activities Relating to Defueling l l (PERAI!ONS l Tasks and Provide Department Level l_ _ _4300 _ _ _,l Programmatic and Technical Direction 1 i I I I mmCER mmcfR mmaR PN0 GRAMS mmaR DECONTAM NATION SilE ENGIMERING K $1GN CONTROL KCGfERY SYSTEMS ENGIPEERING DIKCTOR & SJPPORT 4320 4X0 4350 4360 4370
. Provide Contractor Co- . Provide Techn2 cal . Provide Engineerang, . Provide Department Level . Provide Contractor ordination, Logistace & Enganeering Support and Design and Analytical Planning, Scheduling, Coordination, Logie-field Operatione for De- Startup and Test Services Services Budgeting and Cost tice, field Engineering contamination, Dose Re- Control and Field Operatione duction & Remotely . Analyze Department to Support Decontamine- ; Controlled Devises Schedule or Coet Devie- tion & Fuel Removal tione Operations ! .Propero and Maintain . Construct Recovery Department Level Adminis- Systems trative Procedures . Maintain Recovery ,
i i
. Prepare Proposal Sub- Systeen Not Turned mittele to Outside Over to Site Opere-funding Agencies tiene 1/86 INI-2
~
\ m LICENSING & NUCLEAR SAFETY DEPARTMENT S4206ARY OF RESPONSIBILITIES Provide primary interface with NEC and provide licensing services for TMI-2 Provide independent safety review of procedures, design changes, tests, experiments, etc., which are determined to be review significant Provide Risk Assessment of TMI-2 activities Provide programmatic assessment of nuclear safety at TMI-2 MMOR FUNCTIONS Act as interface with the NKC on licensing matters related to THI-2 Prepare and/or coordinate responses to NRC including I&E bulletins, circulars and inspections Provide administrative systems for control of licensing basis documents, i.e.,
Technical Specifications, Safety Analysis Reports, Technical Evaluation Reports, System Descriptions, and Operating License Coordinate the evaluation and reporting of items under Technical Specifications, 10CFR21,10CFR50.55(e), or other regulations or licenses Support, budget, and monitor the activities of legal consultants for hearings and other licensing activities involving TMI-2 Perform independent safety review of'significant procedures, design changes, tests, experiments, and proposed activities and supplemental safety review of a sampling of other procedures and activities 1/86 TMI-2 Pg. I1
m LICEatSIIIG & 3RICLEAR SAFETY DEPARTMENT - (Continued) i ) Perform prograusatic level independent safety review of snajor recovery programs - Prepare Licensee Event Reports and investigate same Review Recovery Operations Plan surveillance activities and results; perform trend analyses Perform Risk Assessment and Failure Mode Effects Analyses of major TM1-2 activities and systems; provide input to the Of fice of the Director, TMI-2; Project Planning & , ! Analysis; Recovery Programs; and Site Operations departments Review technical assessments of the TMI fire protection program i l i e I i i i 4 1 1/86 TM1-2 Pg. 12 _- - - - - -- 3
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PW3JgCT PIAMellMG AND ANALYSIS DgPARTIENT SIRetARY OF RESPOhSIBILITIES Centralize control and direct the acquisition and management of recovery-related technical data Provide coordinatiun and overview functions in connection with government and industry sponsored programs at TM1-2 Maintain interface and provide support to the Safety Advisory Board, Technical Aasessment and Advisory Group (TAAG), Atomic Industrial Forum (AIF) and other such advisory / assistance groups as required MAJOR FURICTIONS Direct the interface with sponsors of government and industry / funded programs including coordination of proposal preparations and overview of performance Identify, coordinate and document resolution of key technical decisions related to recovery planning Maintain functional end point criteria applicable to major recovery steps Direct and control the acquisition, evaluation, recording and reporting of technical data applicable to recovery - Review recovery scheduling activities, as necessary, to ensure that planning requirements (sequences, priorities, and the like) are appropriately reflected therein 1/86 TMI-2 Pg. 14
. . - . ~
m IME-2 DIVISIWI DIKCTOR TM'-2 4000 0 i l I althAER *Act As Secretary to the SA8 PROJECT PtANNihG & i ANALYSIS 4500 l - 1 l~ ~ P5ilECT'~ ~l l_ _ _ _ _l SUPPORT l . Provide (h-Site Con- ! l l l tractor Administration
- I l_ _ 5 0_0 _ _j i i
! I I i SJetantl50R MANAER Male GA PR(LECI SUPPORI DAIA M4hAE E NI EXTERNAL
- T LAfed! K.
SEeAtICE$ & AhAtYSIS AFFAIRS 4510 4550 4560 4570 - I i . Provide Davision Ischnical .Defane, Control, (btain and .Act as Prime Interfsce with . Develop and Maintain Program
! luriting, Editing and Graphacs Interpret Technical Data to Spenoors of Government and Strategy Services Sapport the Recovery Industry Funded Progrees, in- . Coordinate with Dther Depart-5
.Meantain Technacal Data . Perform Special Studies and cluding the N=::: Contract mente on tower Tier Strategy
- Library, includang Video Tape Evaluations Related to Tectni- . Provide Interface / Support to Plans I and Photo Services cal Data to SAS, TAAG & AIF . Develop tong-ista Strategy for
.Coordanate Sample Package . Coordinate and Control Aegaisi- Ultimate Disposition of the Plant Revioen/ Approval taan Technical Data Regaaeted by
.Coordanate Revisee/ Approval of Enternal Organizations IMI-2 Related Papers /Presenta- . Provide CADD and VAX Computer tions Services for the Recovery Effort "Section on loan to J.C. Devine's i
task force until January 1986 1/86 IMI-2 Pg. 15 ,
. C CPU NuC1. sir TECNNICAL FUNCTIONS DIVISION
- siren &RY OF RESPONSIBILITIES Provide engineering to assure uniform technical and regulatory adequacy of all aspects of nuclear activities, except TM1-2, to provide safe, reliable and efficient operations in accordance with corporate policies and all applicable laws, regulations and licenses.
MMOR FUNCTIONS Perform, manage and direct all out of plant engineering, design and safety analysis. Provide and maintain a qualified staff. Provide technical configuration control for the plants.
- Maintain all plant technical basis and configuration control documents.
Control and perform interface activities with non-financial regulatory groups. Perform plant technical monitoring / assessment / productivity analysis, including major equipment failure analysis. Prepare / review and approve all engineering and licensing procedures and licensing document correspondence and prepare SAR's, Technical Specifications and Environmental specifications. Plan, specify and control hardware and software for plant process, simulation and other real time plant computer applications. Provida overall fuel' management for the plants. Specify, manage, direct all nuclear fuel material, conversion, enrichment and
~
fabrication contractors. Faview and assess the safety significance of operating experience from NRC notices, bulletins, indust ry reports, etc. and provide recommendations for needed actions. 1/86 TF Pg. 1 i h
m - - Provide and direct operating plant shif t technical advisors. Review and concur in all plant operating and emergency procedures and selected other procedures for technical adequacy. Provide project engineering for Technical Functions' sponsored activities and others, as agreed. Review training programs for technical content, as appropriate, and provide technical input for modifications. Plan / direct all startup & test activities. Prepare / recommend / control CPU Nuclear capital budget for plant modifications and studies. Manage and provide chemistry and metallurgical analytical services for 0.C., TMI and the system CPU fossil stations. Establish and maintain plans and schedules, policies, procedures, standards and practices for the Division. Develop, gain approval and operate within approved annual budget, annual operating plan, and the multi year strategic plan. Develop and maintain effective consultation and advice with other Divisions to help assure efficient functioning of CPU Nuclear. Take the lead and coordinate the development of a long range plan for the O.C. and TMI-l plant s.
*See TMI-2 Division Section of plan for technical responsibilities assigned to Director TMI-2 Division.
1 i I i 1/86 TF Pg. 2 i
p . . TECHNICAL FUETIONS OFFICE OF THE PKSIDENT IIDO DI E CTOR TECHNICAL FUETIONS 5000 DIRECTOR , _ PLANNIE 5000 l I I I I I EEIKERifC DIE CTON DIE CTOR DIKCTOR DINLLIUR DIECTOR DI ECTOR KWICES LICENSIE & EEIKERING SYSTEMS ENGIKERING STAR 10P & ENGIKERIE DIECTOR K alLATORY & DESIGN EEIKERING PR(UECT S TEST ASSIRAEE AFFAIRS
$100 5200 5300 5ta00 5500 5600 5700 1/86 TF Pg. 3
.,-s.
ENGINEERING SERVICES DEPARTMENT
SUMMARY
OF RESPONSIBILITIES l Provide the engineering management tools and systems to the Technical Functions division to permit ef ficiency of operations and to provide the interface between the Technical Functions administrative systems and those within GPU Nuclear. 1 MAJOR FUNCTIONS Provide design drawings in support of assigned plant modifications 1 Prepare and coordinate all engineering and licensing procedures and standards Analyze Technical Functions work methods and systems. Recommend changes, as appropriate Provide coordination and consistency in engineering project authorization, planning and scheduling Provide engineering department work load management systems Provide basic engineering data files and maintain all plant technical basis and l configuration control documents Provide technical document release system and configuration control methods Provide engineering project cost estimating Provide capital budget preparation & cost control for plant modifications and studies 1 Provide coordination for Technical Functions OEM budget preparation Provide economic analysis of plant reliability and energy production Perform all GPUNC design and draf ting and prepare as-built drawings within configuration control guidelines Plan / direct development of Computer Aided Design and Draf ting (CADD) Systems Provide integrated schedule and financial forecasting capability for projects Coordinate the Technical Functions review of operating alarm and emergency procedures and training programs. 1/86
,o
D. DI E CTOR TECHNICAL FUETIONS 5(00 . ENGIKERIE TRVICES DIRECTOR 5100
~-
(COsi'UliR AlDEDl -
--_-_____l DESIGN l l DEVEL&KNT l l
1 - _ 1100 - -.I l l l EE. PRUCEIDES EE. PLd JdNING ER. EE. COSI & EE. IMTA & ER. !
& STANDARDS & THE[ULING PRODUCTIVITY C0KIQ1 RATION DESIGN & i MGR. ER. AN4 LYSIS CONTROL ER. DRAFTING
$110 5120 5130 5140 5150
. Prepare / Control .Eng. Project Plane .Eng. Coet .Mmeter Eng. Data .Doelgn & Drafting Engr. & Licensing & Schedules Estimating Files . Field Change l Procedures & .Eng. Work . Tech. Functions .iechnical Docu- Support
- Standards Loading Schedules Cost Analysis ment Release . Modification Turn-
. Corporate Pro- . Schedule Deviation . Cost / Benefit . Plant Configuration over Documentation l cedure Interface Analysis Analysis Control System . Plant Walkdowns l . Work MettuMJs & .Long Range Plan- . Budget Prepare- .As-8ullt Program !
l Systems Analysis ning Sapport tion
- . Divisional Admin- . Project Authori- ,
intrative functions zetion
. Financial Fore-casting 1/86 TF Pg. 5
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LICENSING & REGULATORY AFFAIRS DEPARTMENT *
SUMMARY
OF RESPONSIBILITIES l Assure the continued licensability of the Oyster Creek and TMI-l nuclear plants and provide a technically consistent interface with the various regulatory agencies for these two plants plus Forked River and Saxton. Provide environmental licensing for all nuclear sites including TMI-2 MAJOR FUNCTIONS Provide control and perform interface with non-financial regulatory agencies interfacing with GPU Nuclear including NRC, environmental and local county and city pe rmit agencies and supporting legal services. Manage CPU Nuclear participation in licensing hearings Coordinate all GPUN activities with respect to INPO Obtain all licenses and permits fog nuclear facilities: Federal, State and local Prepare and coordinate approval of responses to regulatory agencies including NRC I&E bulletins, circulars, notices and inspections Provide licensing guidance and interpretation for all aspects of CPU Nuclear regulated activities including the coordination with legal counsel, as necessary Maintain long-range involvement in regulatory affairs, Federal and State register review, trade associations and owner's groups, and assess evolving licensing requirements and risks (current and future) Provide systems for control of licensing basis documents-technical specifications, SAR's, regulatory guides, standard review plans Negotiate, within limits established by management, with regulatory agencies on requirements , schedules or commitments Coordinate the evaluation and reporting of responsible items under technical specifications, t:PDES permits, 10CFR21, 10CRF50, or other regulations or licenses I 1/86 TF i Pg. 6 l
r
- LICENSING & REGULATORY AFFAIRS DEPARTIENT* - (continued)
Concur with important to safety Design Criteria Documents from the standpoint of having addressed all applicable regulatory requirements and licensing commitments Exercise administrative control of amendment requests to the Safety and Environmental Technical Specifications and the FSAR in accordance with 10CFR Interface with and provide support, as requested, to the Supervisor-TMI-2 Licensing Prepare, coordinate, submit comments to industry or regulatory groups on proposed legislation and regulations; establish and maintain contacts with Federal, State and local regulatory agencies Present GPUN positions regarding proposed legislation and regulations to directly influence the final requirements GPUN must meet Provide principal interface with NRC's inspection and enforcement inspector, resident inspectors and indust ry agencies. Resolve issues in apparent conflict with licensing or permit documents or CPU nuclear licensing positions
*See TMI-2 Division Section of Plan for technical responsibilities assigned .to Director /
TMI-2 Division ' 1/86 TF Pg. 7
m - DI E CTOR TECHNICAL FUETIONS 5r00 DIR. LICENSIE & ) K Q1LATORY AFFAIRS Sn00 1 MAN &R MAM ER MANAE R PWR BWR ENVIRONENTAL LICENSING L ICENSING LICENSI8C
- 5210 5220 52MI
. Provide Principal . Principal Interface . Provide Principal .S tain All Environ-
. Principal Inter- .Neintain up-to-Interface with with Regulatory Interface with MIC'S face with Regulatory mental Licensee & date Knowledge of NIC'S IAE Inspectors Agencies Interfacing I&E Inspectors et DC Agencies Interfacing permite and Amend- the Evolving Lican at IMI-l on IMI-l . Coordinate & Evaluate on E mente thereto sing Environment
. Coordinate & Evaluato . Prepare for & Manage Responses to I&E Bul- .Propero for & Manage . Principal Interface . Evaluate future Roeponses to IAE Bul- CPUM' Participation in letine, Circulars, CPUE Participation with Regulatory Licensing Rieke es letine, Circulars, Hearings on THi-l Notices & Inspections in Hearings on DC Agencies Interfacing They Apply to GPUN Notices & Inspec- . Review & Provide Licensing for E . Review & Provide on Environmental . Provide Interprets j tions for TMI-l Guldence Regarding Con- . Assure Compliance with licensing Guldence Iseues tion of Legisla-l . Assure Compliance figuration Management, Corporate Policy & hogarding Configure- . Prepare for & Manage with Corporate Policy tive. Administre-Design Criteria, Mode, Comenitments on DC tion L.--; ..t. Design GPUE Participation tive Regulations &
& Commitments on IM1-1 etc., for IM1-1 Licensing Iseues Criterie, Mode, etc. in Environmental Judicial Decisions Licensing Issues . Assure Compliance with . Stein all NE for E Hearinge .Neintain a Long
.0btain all NFC Licenses Corporate Policy & Licenses & Permite . Assure Compliance with . Review & Provide En- range Involvement
& Permite & Amendmente Commitments on IM1-1 & Amendmente thereto Corporate Policy & Con- vironmental Licensing in Regulatory thereto for TMI-l Licensing Issues for E mitments on E Licensing Guldence Regarding Con- offairs issues figuration Management, . Establish & Mein-Design Criterie, Mode, tein Close Contact etc. with Federal, Stat
. Assure compliance with & Local Regulatory Corporate Policy & Agencies Commitmente on En- .Present GPUN'S vironmental Licensing Position on Draft iseuse Legislation /Regula tiene 1/86 TF Pg. 8
at ,r
- ENGINEERING & DESIGN DEPARTMENT ,
SUMMARY
OF RESPONSIBILITIES Provides a centralized technical capability in the conventional engineering disciplines and is responsible for the technical performance of components and syste=3 in the plants within their area of expertise MAJOR FUNCTIONS Provide design drawings and specifications in support of plant modifications 4 4 Maintain central CPUN technical capability in disciplines assigned to the department Investigate plant system and equipment failures, retain cognizance over technical performance of plant hardware Provide Technical Functions review / concurrences of maintenance programs / procedures and other assigned plant procedures, as appropriate Provide Technical Functions review / approval of work performed by outside engineering firms, as appropriate Support plant outages within overall CPUN priorities Perform GPUN engineering in support of design within technical disciplines assigned to the department Provide tire protection support l Provide the generating stations (both fossil and nuclear plants) with metallurgical laboratory services and materials and welding engineering services Provide chemist ry requirements, specifications and engineering support to fossil and nuclear plants l l l l l 1/86 TF Pg. 9 ( l
m DIKCTOR IECHNICAL FU KT10NS 5(00 j DIR. ENGIEFRIE
& DESIGN 5'00 l
l- ~MGi4ER~ ~l _____J PECIAL I l PRaKCTS l L _ t m_ ---I I I I CK MI SIRY/ MANAGER MANAG R FLAllDS SYSTEMS MAIE RI ALS ENGlKERING ELEC. POK R & DIRECTOR DIKCIOR KCHANICS INSTRIENTATION 5 113 5320 5350 5300
. Field Servicee .Cheelcal Pro- .Analy2e/ Support .Moch. Analysie .Elec. Power . Mach. Compo- .Priesty & .Weste Mget.
.Plent Procedure cessee -oper. Chem. . Civil /Structu- . Instr. Applica- nonte Specs & Secondary Plant . Solidification Review . Water Cheelstry -Environ. Chem. rol Eng. tion Application Fluid Systems Systeme I
.Tosell Plant Spec -Fosell fuels . Fluid Meche. . System Control . Performance .HWAC . Packaging Sapoort .Weter Treat- -lubricante Analysis . Plant Procedure Evaluation . Fire Protec- . Liquid Red
. Material ment Eng. -Resine Review . Maintenance tion Treatment Applicatione . Waste Water -Water Chem. Sapport .Materiale . Plant Pro-
. Failure Analyste Treatment Eng. .Analytacal . Plant Procedure . Handling cedure Review
.Motellurgical . Plant Procedure Procedures Revlow . Plant Procedure Lab Services Review Review
. Welding Engineering
.Neteriale l Engineering 1/86 TF Pg. 10
- p. * '
SYSTEMS ENGINEERING DEPARDIENT SUml&RY OF RESPONSIBILITIES Provide special analytical skills in reactor physics, plant dynamics, risk analysis, human engineering, plant computer applications and radiological engineering Provides direct full time, in plant capability in support of operations and is a key contributor to the review of operating procedures, plant performance and training programa MMOR FUNCTIONS Analyze overall GPU Nuclear plant technical performance. Recommend actions, as appropriate Provide nuclear fuels, fuel materials, overall fuel management strategies and basic core physics capability l Provide Technical Functions concurrence of assigned operating, alarm, and emergency I procedures and the technical content of training programs i l Provide technical expertise in risk analysis, human factors engineering, radiological i engineering, and plant dynamics and simulation Staff, operate, program and upgrade of plant process computers Maintain software and sof tware configuration control of training simulators and plant process computers Staff, qualify and direct shift Technical Advisors Assess the safety significance of operating experience from NRC notices and bulletins, indust ry re po rt s , et c. , and recosamend appropriate actions 1/86 TF Pg. 11
I f. DIECIOR i IECHNICAL FUETIONS 5(00 DI K CTOR SYSTEMS ENGIKERING Sd 00 l i MICLEAR ANALV$1S MANAGER 1.0WuTER MMt dZR MANAGER
& FUELS DIKCIDH APPLICATIONS & RISK PLANT FUMAN ENGlEERING ANALYSIS ANALYSIS j 5410 5420 5430 5460
{ . Safety Analysis . fuel Project . Fuel Project . Operating Plant .0perating Plant . Reliability . Plant Performance
. Dynamic mdeling Myst. for THI-l Mget. for E Computers IMI-l Computers E Data Bank Analysie
- . Plant Control .TMt Eclear .E Nuclear Analysis . Computer Pro- . Computer Pro- . Risk Analysis .LER Review i Systems Analysis .uC Reload Eval. gramming gramming . Failure Modes .STA (TMI-l & E) l . Plant Procedure .TMt Reload Eval. .iech. Direction of . Simulation . Simulation & Effects Ana. . Plant Procedure Review . Tech. Direction of DC fuel Suppliers ra=piters TMI-l Computers DC .Probaballetic Review TMI Fuel Suppliers .UC Control Rods & . Improved ra=Puter . Improved Computer Risk A- .t
.iMI Control Rods Core Consumables Systems Systeme
& Core Consumables . Shielding Calcu-
. Radiological Source lations haan Factors Tern Analysis . Radiological Source . Control Room Criteria I . Shielding Calcu- Term Analysis . Human Eng.of Plant Mode j lations . Plant Procedure . Computer Human Communi-
. Plant Procedure Review catione Review
- Reload Methodology
. Analytical Methode Development
- . Procedure Development j - helear Fuel Resources
. Fuel Inventory Management
. Uranium Enrictament Conversion
. fuel Budgets & Forecasts
. Spent Fuel Storage Tech.
1/86 IF Pg. 12
ENGINEERING PROJECTS DEPARTHENT
SUMMARY
OF RESPONSIBILITIES Manage all assigned operating nuclear engineering projects to ensure completion of every authorized project in a technically competent manner, on time and at the most reasonable cost consistent with safety, quality and schedule requirements MMOR FUNCTIONS Manage, coordinate or direct the engineering effort required for any assigned nuclear station physical plant modification, addition or major non routine repairs Provide on-site coordination of Technical Functions division personnel and activities (except fulltime, on site functional personnel directly supporting operations; i.e., l start up & test, computers, STA'S, plant analysis, licensing) l l Recommend and control the CPU Nuclear Corporation Capital Budget for plant modifications and studies Recommend and function in accordance with approved priorities for engineering projects Functions as project managers coordinating interdepartmental, interdivisional and external activities f rom conception of plant modifications through turnover for ! opera t ions Provide Technical Functions approval and release of detailed engineering for modifications performed by outside engineering firms Provide Project Management for engineering activities association with Saxton i i < l I i 1/86 TF Pg. 13 I
=
DI KCIOR TECHNICAL fUfCTIONS 5f00
! DIII CTOR EEIKERING PR(DECTS 5'00 l
I mm CER I mh &R MMt ER fMNAGER OYSTER CKEK UYSTER CREEK TMI-l !PECIAL Of;IKERING EXPAM)ED SAFELY EEIKERING PROJECTS PR(DECTS SYSTEMS FACit!TY PR(DECTS 5510 5515 5520 3 5550 l . Direct & Evaluate DC . Direct & Evoluete . Direct & Evaluate THI-l j Project Activities
. Direct & Evoluete Project Activities for Project Activities Pr m Project Activities
; . Assure Coopliance with the E Expanded Safety . Assure Coopliance with i For Simulatore, Volume Corporate Priorities & Systems facility including Corporate Priorities and Commitmente on E En-Reduction Solidification, New Diesele and Electrical Commitmente on THI-l Redemote, Sexton and gineering Projects Switchgear tidditions Engineering Projecte j . Compile and Control the feargency ^ 1 e recility
. Assure Coopliance with . Compile and Control the . Assure Coopliance with I OC Capital Budget Corporate Priorities & TMl-1 Capital Budget I Corporate Policies and
. Coordinate Technical Commitmente on E Ex- . Coordinate Technical Commitments for en--an functions 01violon panded Safety Systems functions Division Projects
! Interfaces and Activities Facility Project Interfaces and Activities et the Station Site et the Station Site
. Maintain Approved Site .Meintain Approved Site Piene Plane l
I I ( l I 1/86 TF Pg. 14
START-UF & TEST DEPARTNENT SIRGIARY OF RESPONSIBILITIES
! Provide and perform a start up and test function for CPU Nuclear during operation, refuelings and major outages to assure new or substantially modified plants, facilities and systems are systematically tested, documented to conform with technical requirements and turned over to plant operations MA.JOR FUNCTIONS 4
i Prepare test plans and implementing procedures l i Direct testing, ensure test engineers have required special training and skills needed to perform this testing Ensure preparation of test documentation, compile same for turnover to operations Coordinate technical acceptance of testing Provide and obtain testability input to design engineering for plant modifications I l l i l \ l l 1/86 TF Pg. 15 1 \
DI K CTOR ! IECHNICAL FU8CTI(BsS 5(00 DIK LIUit START-UP & TEST 5(00 1 MMe Clk MMtER TMI UNIT 1 DVSTER CREEK l START-UP & IEST START-UP & TEST ; I
% 20 WG l
. Test Planning . Test Planning l .Toet Direction
, .Teet Direction 1 . Test Procedures . Test Proceducee
,i . b retione Input to Engineering .operatione Input to Engineering l . Turnover to Operations & Test . Turnover to @ retions & Test l Data Package Date Package i
I l l l l i I
! 1/s6 TF
, Pg. 16
\ p 1
ENGINEERING ASSURANCE DEPARTNKMT SUges&RY OF RESPONSIBILITIES Develop and implement company wide programs to ensure compliance with fire protection as addressed in 10CFR50 Appendix R and environmental qualification of equipment (10CFM50.49) i Develop lists and administrative controls to address quality classification, engineering data and vendor documentation i NMOR FUNCTIONS i Ensure electrical components required for shutdown are qualified to the EQ rule Establish and implement system to maintain Appendix R compliance and overall fire hazards analysis Establish and maintain a component level quality classification list for each plant l Establish and maintain a computer oriented GPUN technical data base at the ! component level l Provide a central source for maintaining critical engineering data 1
- Establish and ensure implementation of a system to control vendor documentation I
l i i I i f I l ! 1/86 j TF Pg. 17
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CPU IRJCLEAR NUCLEAR ASSURANCE DIVISION S*dlet&RY OF RESPONSIBILITIES Ensure that an appropriate quality assurance program, whose scope covers all the systems and activities that affect safety and reliability, is established, implemented
' and verified in accordance with corporate policies, applicable laws, regulations, licenses and technical requirements.
1 i Selectively review both nuclear station and corporate activities with the aim of identifying areas where changes could lead to improvements in the nuclear safety and/or reliability of plant o perat ions. Provide training and education of corporation personnel, as needed, to carry out their duties and to meet Corporate policies and all applicable laws, regulations, licenses and technical requirements. Assure that a high level of emergency preparedness is maintained in accordance with corporate policies and all applicable laws, regulations, licenses and technical requirements. l NAJOR FUNCTIONS Establish and maintain plans and schedules, policies, procedures, standards and practices for the Division , Provide and maintain qualified staff I l Develop, gain approval and operate within approved annual budget, annual operating plan, and the multi year strategic plan Audit, monitor, inspect, evaluate and assure that all activities having the potential for com- omising nuclear safety are adequately addressed Develop and implement necessary training programs Develop the site emergency plans, implement procedures and plan, conduct and evaluate emergency drills Develop and maintain ef fective consultation and advice with other divisions to help assure efficient functioning of CPU Nuclear. 1/86 HA Pr. I
[., n Office Of The President l DI KCIOR NJCLEAR ASSJRAEE 6000 j l~ ~M R ~~l
- _ _ _ _ _ .. _lADMINISTRATIVE l l TRVICES l l_ _ ELD _ _ _l l
I I I l DIKC TOR DIE CTOR NJCLEAR SAfEIV stueuzR QU Alliy TRAINIE. & ASTSSENT E E RGE EY ASSIRAEE EDJCATION DIE CTOR PKPANDESS 6100 6200 6 M1 6400 4 I i 1/86 l NA 1 Pg. 2
ADNINISTRATIVE SERVICES DEPARTMENT S14etARY OF RESPONSIBILITIES i Provide management services and consultation to the Director, Nuclear Assurance and Department Directors on directing administrative program controls for the Nuclear Assurance Division Provide leadership in the development of programs, policies and procedures to enhance the capabilities of specific Nuclear Assurance functions Coordinate the Division's planning activities with those of other divisions Establish ef fectiveness programs which promote good management practices and monitor consistent application of methods and procedures among Nuclear Assurance departments at all CPUN sites l MAJOR FUNCTIONS Establish programs to improve Division effectiveness and assure consistent application of management and administrative methods within Nuclear Assurance Establish and maintain uniform administrative policies, procedures and practices within Nuclear Assurance Division I Provide leadership to enhance the functional capabilities of the Division through the management of special projects i. 1 Oversee appropriate dissemination of management information and assure accurate and timely preparation of corporate management reports i i Provide corporate reporting and special project and staff support for Division management Coordinate the developa:ent of long-term plans, goals and budget controls for Nuclear Assurance Ensure the effective utilization of the Division's manpower resources through planning and control programs. 1/86 NA Pg. 3
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N Aff e W N W 3 $m (- Ma GG8 =3 W=u da3g 3-E ES 25W a Q R l l l O e
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QUALITY ASSURANCE DEPARTMENT SUNNARY OF RESPONSIBILITIES Develop and administer QA plans and procedures required to assure that all CPU nuclear activities provide the required high degree of safety and reliability Monitor and evaluate activities of GPUN to assure that they provide the required high degree of safety and reliability and are carried out in accordance with all applicable laws, regulations, licenses, corporate policies and other requirements Identify quality problems, and initiate, recommend or provide solutions through designated channels and vccify implementation of resolutions Develop and administer the CPUN Nondestructive Examination Inservice Inspection and Weld Programs Perform evaluations on a planned and periodic basis to verify that the Quality Assurance Program is being ef fectively implemented Stop work on nonconforming materials or activities Initiate unit shutdown recommendations when warranted by a safety concern MAJOR FUNCTIONS Develop the plans and procedures necessary to fulfill CPUN QA responsibilities. Provide for the monitoring and evaluation of the implementation and effectiveness of j the CPUN QA program by means of: I
- Review
- Survey
- Audit
- Surveillance
- Monitoring
- Ins pect ion of all organizations, contractors and vendors for all important to Safety and High Reliability activities.
1/86 NA Pg. 5
r... QUALITY ASSURANCg DEPARTHENT - (continued) Stop work or further processing, delivery, installation or take other warranted actions on nonconforming materials or activities Initiate unit shutdown recommendations when warranted by a safety concern and obtain , unit shutdown with appropriate upper management concurrence Provide for the review and acceptance of contractor and vendor Quality Assurance Programs within the scope of the Quality Assurance Program ' Provide for the review and acceptance of procedures prepared by other than QA organizations within the scope of the Quality Assurance Program Direct and manage the Quality Assurance Department Provide a working interf ace and line of communication with other divisions and other appropriate indust ry and regulatory groups for all QA matters
- Develop and maintain nondestructive examination practices and procedures in support of
- inservice inspections and installation inspections i
Establish with Training and Education, the scope and content of an indoctrination and training program for QA and QC personnel Develop and maintain welding procedures, control and qualification programs consistent i with engineering requirements Develop and maintain inservice inspection activities to assure Regulatory Complisace and meet plant operational needs l Assure that QA indoctrination of appropriate personnel outside of the QA organization
! is provided Issue periodic reports to the I
i - Of fice of the President, I - appropriate Unit Vice-Presidents, and ) - CPUNC Board of Directors I on the status of quality activities. l 1/86
- NA l Pg. 6 1
QUALITY ASSURANCE DEPARTBENT - (continued) Immediately notify the Of fice of the President and appropriate Unit Vice-President of any significant, quality related problem or deficiencies Provide for QA review and acceptance of design and engineering documents Provide for QA review and acceptance of procurement documents within the scope of the QA program Provide for and maintain QA records generated by QAD until turnover to document control for storage. I k i L j 4 r 1 i 4 I j i 1/86 NA l Pg. 7 \
- r.
- DIRECIDR MICLEAR ASSIRAEE 6rgjo DilECTOR SIALIIY I
ASSARAEE j 6100 l I MANAMN MANAM R MAN 4GER SPECIAL MUt ER Mut ER IMIQA E QA PROCESSE S QA PRG; RAM QA DESIGN & Muu/WS mud / GPS 'a PROGRAMS K V. & AIDIT PROCUKENT i j 6110 6130 6150 6160 617e
.QA Program .DA Program .Non Destructive .QA Audite .QA Design Engineering i Administration Administration Examination (M)E) . Nuclear Euel QA (Corporate)
} .QA Monitoring .QA Monitoring . Weld Engineering .QA Program De- . Procurement i .QC Inapection, NUE .QC Inspection, l@E . Inservice In- velopment Document Review I . Site Program / Pro- . Site Program / Pro- apection (151) .QA Department . Supplier Evaluation i cedure Review cedure Review .Meteriale tsalification . Vendor Surveillance
.QA Systems Evalu- .QA Systems Evalu- Support to QA .Special QA Pro- .Special QA Projecte
{ atione atione gram Evaluetione .Ergineering Procedure
- .QA Design Engrg. .QA Design Engrg. . Corporate QA Pro- Review j . Procedure & Docu- . Procedure & Docu- gres/ Procedure l ment Review ment Hewiew Review j .QA Trending .QA Irending . Topical QA Plan j .IMI-2 QA Project j Engineering I
l 1 l I/86 l l Pg. 8 i l
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- TRAINING & EDUCATION DEPARTIEarf 844GIARY OF RESPONS151LITIES Provide training of corporation personnel, as needed, to carry out their duties and to meet corporate policies and all applicable laws, regulations, licenses and technical requirements. Provide corporate-wide consultative services on all other training related matters MAJOR FUNCTIONS Ensure that ef fective training prograns are available for employees to meet corporate policies and comply with all applicable laws, regulations, licenses and technical requi rement s Ensure a highly qualified staff to effectively teach and communicate the course content ,
to employees ~ Develop an effective simulator training program for the training of CPU personnel that meets or exceeds the state of-the-art for the industry Ensure efficient and effective facilities to support the training needs of the nuclear generating stations Ensure that accurate and timely information is sent to management so that potential problems can be minimized Maintain strong communications and cooperative links with CPUN Operating Divisions, Regulatory Agencies, INPO, eel, Universities, regional / national utility organizations and other utilities Monitor and evaluate the activities of the Training Advisory Council. I i, f 1/86 NA l Pg. 9
.O DIK CTOR NJCLEAR ASSJRAEE
! MM DIECTOR TRAINING /EIUCATION , 6:90 _ _ _g _ _ _ ______l TRAINifG l , 1 ADWISORY l l_ _ CDLEE_ _1 T I M4le ER Mut ER NANAGER MMeER PLANT TRAINIE PLANT TRAINilC COIPORATE EIUCATIONAL ) TNI E TRAINING DEVEL(PsfMT 6210 6230 6250 Am I ) . Training Programe . Training Programs .Mer=-; - ,t Development . Educational & Research j -Operator -Operator Programs Development I -Maintenance -mintenance .L -; .t Technical . Testing
-Technical -Technical Training . Accreditation
] -Red Control -Rad Control . Engineer Training . Instructor Development l -Chemistry -Chemistry -Plant Technical .Dugree Programs I -Protection -Protection Staff .Advloory Counci! .
-Simulator -Simulator -Corporate Engineering . Educational Assistance j -Et -CEI -New Engineers . Audio Visual j .STA Training l
. Coordinate Generic l Training Programs I
l 1/86 j NA j Pg. 10 [ \
r . . BRICLEAR SAFETY ASSESSMENT DEPARTIENT SINAGARY OF RESPONSIBILITIES Identify problems in nuclear plant design, operations, maintenance and man uschine interactions which have a potential for compromising nuclear safety of the nuclear plant, station personnel or the general public; make recosamendations for solutions and/or improvements MAJOR PUtiCTIONS
- Investigate, assess and recommend changes in administrative'or functional controls required to assure nuclear safety 4
l Provide overview and direction of 10SRG to help ensure the technical adequacy of j nuclear plant procedures, operations, technical specification changes and tests Provide overview and direction of CNSRG to help ensure the nuclear safety adequacy of corporate and support division pro <:edures and operations Monitor and evaluate trends in activities which have the potential for compromising nuclear safety MSAD Director serves as Vice Chairman of GORBs Serve as an of fice of Ombudsman for all members of CPUN having a concern for nuclear plant or personnel radiation safety > 1 t l I i 1/86 1 NA
. Pg. 11 4
,O DIRECTOR f4)C1 EAR ASSARAEE 1
6000 I IWCLEAll SAFEIV
; ASESSENT j DEPARTE NT DIE CTOR l 6300 l~ ~ ~ ~ ~ ~l . Investigate Employee.itaclear Safety Concerne
__,____l OpeJDSMAN I .Recommand Corrective Actions l l .r-micate Resulte I _ 6300,,,, _ _I I E.R. S ETIV fOR. S EE T Y DER. SAFEIV i REVIEW IMI-I REVIEW DC KVIEW-CORPORATE c (10RSG) (10RSG) 6310 6330 6350
.Evoluete Procedures . Evaluate Procedures . Corp. Sofety Overview
. Evaluate Plant Operatiotas .Evoluete Plant Operations . Staff Support for Henege-
.Aesese Plant Safety .Assese Plant Safety ment Directed Safety
, . Assess Plant Performance . Assess Plant Performance a.-%te , . Review Tectnical . Review Technical . Coordination of the Nuclear Specification Changee Specification Changes Safety deview Procese 1 i i 1/86 N4 ) Pg. 12
l (~T l EMERGENCY PREPAREDNESS DEPARTMENT SUMKARY OF RESPONSIBILITIES l l Assure that Oyster Creek and TMI Emergency Plans and Preparedness Programs are in i accordance with corporate policies and all applicable laws, regulations, licenses and I l technical requirements l Provide support and guidance in the Emergency Planning area for the Three Mile Island and Oyster Creek Stations Assure the maintenance of a high state of Emergency Preparedness at Three Mile Island and Oyster Creek Stations MAJOR FUNCTIONS Coordinate emergency planning between the Three Mile Island and Oyster Creek Stations Monitor, evaluate and assure that both Three Mile Island and Oyster Creek Stations have emergency preparedness programs that are coordinated, maintained current and assure a high state of preparedness Assure that Three Mile Island and Oyster Creek Stations' Emergency Plans are consistent with the latest requirements of the NRC and with the FEMA approved Pennsylvania and New Jersey state, county and local emergency plans
' Interface with the Nuclear Regulatory Commission, Federal Emergency Management Agency, State and Local authorities in emergency planning areas Interface with other utilities and indust ry groups in the development of emergency planning concepts and standards Conduct special, independent inquiries into events resulting in actual implementation of the Emergency Plan or other emergency preparedness-related issues, as appropriate and prepare special reports and evaluations for Senior Management which address the appropriateness and adequacy of response Oversee the maintenance of the station emergency communications system and coordinate necessary upgrade or redesign with the Telecommunications Department Provide support and coordination necessary to assure a high state of offsite emerdency readiness (state and local governments)
Assure the operability of the Offsite Prompt Notification (Siren) System 1/86 u.
o . . DI K CTON M)CtEAR ASSARAEE i M OO MANAER EEREEY PKPANDESS GlQ l l EKHGEfCY i EKHGEEY PREPAKIMSS EN PKPANDESS M;R
; IMI (E 6410 6430
. Emergency Plan Development . Emergency Plan Development Coordination with State & Local Coordination with State & Local Governmente implementing Governmente Implementing Procedures, Plane & Scheduling Procedures, Plane & Scheduling Drille Drille
. Maintain Emergency Preparedness . Maintain Emergency Properedness
.0ffeite Emergency Preparedness .0ffeite Emergency Preparedrwee Progrene Programe l
I l .l t I. 1/86 I
- Pg. 14 i
_ _ . - - _ _ _ =
g . . GPU NUC1. EAR ADMINISTRATION DIVISION S1496&RY OF RESPONSIBILITIES Establish and implement uniform policies and programs in Materials Management. Human
- Resources, Security, Operations Analysis, Information Management and Strategic Planning to help achieve Company objectives in accordance with corporate policies and all applicable laws, regulations, licenses and technical requirements.
MAJOR FUNCTIONS l Provide and maintain a qualified staff Provide cont racting, procurement, warehousing and inventory control services Develop and administer the security program Develop and administer a comprehensive Ikaman Resources Management function I Provide operations analyses i Develop and coordinate CPUN's strategic planning process including issues management, and assure its integration with other levels of planning within the Company i Manage GPUN information management centers and coordinate CPUN policies and procedure system j Establish and maintain plans and schedules, policies, procedures, standards and practices for the Division Develop, gain approval and operate within approved annual budget, annual operating i plan, and the inulti year strategic plan I Develop and saaintain effective consultation and advice with other Divisions to help j assure efficient functioning of GPU Nuclear l l l l 1/86 Admin j Pg. 1 I l 9
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p ~ ' STRATEGIC P1ANNING AND ADNINISTRATIVE PROJECTS DEPARTMENT SUNKARY OF RESPONSIBILITIES Develop and coordinate implementation of ef fective strategic, annual corporate planning ' processes, assuring their integration with other levels of planning within the Company. Address and make recommendations for solving unusual administrative problems. MAJOR FUNCTIONS i l Develop, in conjunction with senior management, the major strategic issues the company faces. Assess their potential impact and document strategies for ef fectively managing those issues Prepare the Strategic Plan for senior management review and concurrence, considering strategic issues previously identified, consistent with Company mission, plant long range / operational planning and financial planning Coordinate the development of the annual Corporate Objectives and Coals. Dra f t Corporate Objectives and Goals for senior management concurrence. Assist with Divisional objectives and goals. Track and periodically report progress toward objective / goal accomplishment Prepare the CPUN Board Action Item Status Report and the GOR 8 Action Item Status Report for 0/P review i Investigate and recommend solutions to unusual administrative problems, as requested by Director, Administ ration or 0/P 1/86 Admin Pg. 3
(. , r l l DIRECTOR ADMINISTRATION l 70f 0 l i b j M;R. STRATEGIC PLANNilC & ADMIN. PRa)ECTS l 7010 i j . Strategic Iseue Identification i
. Strategic Plan Preparation and Coordination
. Annual Corporate Objective and Goal Program j . Action Itse Status Reporte (GPUN Board, GORB)
- .Special Admin. Projects e
1 l I i i
; 1/86 j Admin j Pg. 4
p, . . INFORMATION MANAGEMENT CENTERS DEPARTMENT SUM 4ARY OF RESPONSIBILITIES ^ Plan, organize and direct the activities of the company's Information Management Center including the coordination of the Corporate Policies, Plans and Procedural System and other support programs and services to ensure that the Corporation's informational needs are met. MAJOR FUNCTIONS Plan, organize, control and manage the company's information management centers. Provide and maintain a qualified staff Provide and coordinate information storage / distribution, information support and data management services to all Divisions Ensure the effective management of the Corporate Policies, Plans and Procedures System and other support programs and services Develop, implement and monitor procedures and programs related CPUNC's office services ! systems, i.e. forms control, Correspondence Tracking and Word Processing equipment and Word Processing training Ensure that record storage and distribution meet legal and regulatory requirements for storage, retention periods, quality criteria, etc. as well as Company and/or CPU standards and practices, i.e. Computer Assisting Indexing and Retrieval System Plan the future direction of the Information Management Centers and ensure that emerging technologies and regulatory changes and revisions are identified and incorporated into existing system and practices. s 1/86 Admin Pg. 5
e 1 l DIRECTOR ADMINISTRATION 70f 0 i MANAER I I KORMATION l MANAEENT CENTERS 71(0 4 I I j' PARSIPPANY TMI OVSTER CREEK IE MANAGER IE MANAER IIC MANAGER 7131 7132 7133
.Recordo Storage / Retrieval .Recorde Storage / Retrieval .Recorde Storage / Retrieval
.Dete Management (IUE) .Dete Menegement (fuE) .Deta Lanagement (RJE)
.CARIRS .CARIRS .CARIRS
.Micrographics .Micrographice .Micrographice
. Technical Libraries . Technical Library . Technical Library
. Library Network Support . Word Processing Centers / .Nord Processing Centers /
j . Word Processing Centers / Training and Equipment Training and Equipment Training and Equipment Management ;; 1; .t Management .Reprographice .Reprographics i . Procedure Distribution / Control . Drawing Distribution / Control . Drawing Distribution / Control
. Procedure System Coorgination . Procedure Distribution / Control . Procedure Distribution / Control l
1 1 1/8e Admin Pg. 6
i . MATERIALS MANAGEMENT DEPARTHENT SINetARY OF RESPONSIBILITIES Provide responsive and cost effective contracting and procurement, contract administration, warehousing and inventory control services to the plants and support divisions of the Corporation. MAJOR FUNCTIONS Solicit, evaluate, negotiate and issue contracts / purchase orders for the acquisition of materials, equipment, fuels, services and construction for all plants and support divisions Administer and expedite contractor performance including resolution of contractor claims, QA receiving deficiencies, warranty issues and allocability /allowability of costa Receive, inspect, store and issue purchased material and equipment and maintain optimum warehouse inventory levels Develop and administer General Terms and Conditions which assure responsive and timely contractor / supplier compliance with cost, schedule and technical requirements and initiate corrective actions, where necessary, to resolve deficiencies and prevent recurrence Coordinate with requisitioners on future requirements for material and equipment, implementing a Materials Requirement Planning approach and assuring the availability of these items in the quantity and quality required Arrange for employee travel and lodging accommodations Support special Corporate initiatives in areas such as the Pooled Inventory Management and Automated Materials Management Systems. i l l 1/86 j Admin i Pg. 7
p ' DIK CTOR ADMINISTRATION 7f 00 DInLLiun MATERIALS MANAGEKNT 7PDD I I DIECTOR MANAGER MAN 4GER CONTRACTS PREllE KNT MATERIAL CONTR(L
& MAK MQlSING 7210 7220 7230 .Propero Requeste . Provide . Procure Equipment, ." - - - ,t o f . Receive, Store &
for Side /Proposele, Assistance to Spare Parte, Supplies Company Were- leeue Meteriale, Perfore Source Selec- Requisitioning and Services houses Sapplies and Equip-tion, Negotiate and Activities Through . Material Expediting . Inventory Con- Mont Amerd Contracts for Advanced Procure- . Procurement Planning trol, Including . Inventory Were-Construction Pro- ment Planning Pro- Meterial Sourcing and Establishing Re- houses and Validate reselonel Services, ceas & Consulta- Sapplier Performance Order Pointe Materiale Status Mejor Equipment and tion Review . Control Con- . Coordinate With Users Consultants . Monitor Contractor .Value Analysis =Mles for on future Inventory
. Negotiate and Issue Performance in . Traffic Management Support of Site Requirements & Out-Changes to Existing Terms of Cost, and Shipping Coordine- theretione dated Materiale Contracts Schedule and Per- tion . Develop Inven- . Control Construction . Administer Terme and formance .iravel/todging tory Usage and Materiale and Non-Conditions of Con- . Initiate Correc- Services Turnover Rates. Inventory Consumables tracts, including tive Action to Re- . Coordination of QA Maintain (5timum (Director Turn-Over)
Warranty and Coat solve Deficiencies Receiving Deficiencise Stock tevole . Development of Stores Allowance Provisione and Prevent He- . Development of Auto- bdule of Automated currence meted Meterials Manage- Meterials hi---, -
.t ment System's Procurement System Module 1/86 Admin Pg. 8 n -
C ' IRad&M RESOURCES DEPARTHENT SIRetARY OF RESPONSIBILITIES l Accountable for planning, directing and administering all aspects of a comprehensive l Human Resources Management System to enable the Company to attract, motivate and retain
! higher caliber employees within the parameters of the Corporation's objectives and I
goals in compliance with all legal requirements and consistent with the CPU System Human Resource policies Accountability for all GPU System labor relations is vested in the appropriate Operating Company i Responsibility for contractor labor relations is vested with Maintenance, Construction
& Facilities MAJOR FUNCTIONS Maintain close communications and coordination with Operating Company Human Resources Departments to assure consistency of CPUNC personnel actions with System Policies &
Procedures i l Provide leadership in the development and implementation of policies, procedures and ! programs that help ensure the organization manages its human resources to meet ! organizational and business needs and achieve high standards of professional and managerial competency l Provide leadership to help establish, implement and manage manpower planning and staffing programs and selection, recruitment aad hiring practices to ensure that Corporate manpower requirewents are met in accordance with all pertinent regulations and codes Identify, evaluate and recommend to management future development needs, organizational configurations and manpower requirements to optimize the use of the Corporation's Human Resources Identify general supervisory, management and personal professional skills training needs for the Corporation and work with Training and Education to assure adequate content and availability of such programs. 1/86 Admin Pg. 9
~ -. -
Himg&M RESOURCES DEPARTM NT - (continued) Conduct surveys to determine skills, attitudes and career aspirations of employees. Develop and manage systems designed to provide prompt resolution to Company employee problems or concerns Establish and maintain, through job specifications and descriptions, job analysis and evaluation procedures, an equitable Compensation and Benefits Program for employees to ensure practices are internally consistent and externally competitive Administer the wage and salary Pay for Performance and the Performance Appraisal Programs for exempt and nonexempt employees, including annual merit and promotion budgets Provide objective expertise in areas pertaining to Human Resources management, planning, development, counseling, appraisal, measurement and motivation Develop and administer employee indoctrination, orientation and retention programs, career progression planning program and counseling and employee assistance programs Develop and maintain a comprehensive baan Resources Information and Planning System Update and assure the integrity of the GPUN input to Payroll / Employee Information System (PElS) data base and generate special and recurring Human Resources Management , reports to upper management Develop and monitor equal employment and affirmative action programs which are consistent with Corporate policies and all applicable government regulations Maintain Organization Plan, Organization Chart and Human Resources Policies and Procedure Manuals for headquartets and plants. 1/86 Admin Pg. 10
I DIK CTOR ADMINISTRATION 7000 DIKCTOR MJMAN NESGJACES 7300 l I AK A Nue4CER AKA MJeAGER AKA M Jt4GIR OK.ANIZAll(Di NUE RR MJMud ESGJACES MJMAN KSUUNCES NJMAN KSGJACES DEVEL EPENT CODPENSATION 4 PARSIPPANY/KADING TML OC DIK CTOR NJMut KSGlKES ADMINISTRATION 7310 7320 7330 7370 7371
.Esployee Relataans . Employee Relations . Employee Relatione . Programs and . Organization . Salary Budget .llpgrade &
. Recruitment / Employ- . Recruitment / Employ- . Recruitment / Employ- Systees to Up- Plan Controle Maintain PE15 ment ment ment grade and In- . Organization . Position Co- . Turnover
. Employee Counseling . Employee Counseling .Emplovee Counseling prove Organi- Chart scriptions/ Analysis
.Aree Pamp=osation . Area Compensation . Area Compensation zational Per- . Develop Per- Specificatione .Menpower Re-Adminsstration Adnanastration Adminletration formance formance Ap- . Performance porting
.Senefit Admin. .Benefat Admin. .Senefit Admin. .Esployee At- preimal System Appraisal . Coordinate &
. Area EEQ/AAP Pro- . Area EEQ/AAP Pro- . Area EE0/AAP Pro- traction end . Review /laprove .Surveye & Consolidate gramo stans grams Retention Pro- Employment Studies EEIVAAP Pro-
. Orientation & Ir>- .Orientataan & In- . Orientation & In- grams Transfer & Pro- . Carrier Liel- grams doctrination doctrination doctrination . Establish Man- motion actions son & Con- .Recommand In-
.Aeninaster Internal . Administer Internal .Adminaster internal power Planning . Coop /Co!!ege tract Renewsle provements to Promotional Progree Promotional Program Promotional Program Systeen Relations .ERISA Compli- Benefit & Com-
. Employee Records & . Employee Records & . Employee Records & .Succeselon . Identify Nun- ence pensation Pro-Data Base Mainton- Data Base Mainton- Data Bees Mainton- Planning technical train .Premius & Claise grams ance ance ance . Career Pathing ing and develop- Analysis . eel Test Coor-
. Relocation Program . Relocation Progras . Relocation Program . Counsel on Or- ment raede . upgrade Benefit dination Administration Administratton Administration genizational .Nork with T&E to A M n. Systems .HR Policies &
. Temporary Clerieel . Temporary Clerical . Temporary Clerical Structure Assure Adsupete & Measurements Procedures Pool Pool Pool Content & Avail-
. Employee r - mie.- . Employee e - mica- .Esployee Communica- ability of Train-tions taons Lione ing and Develop-mental Programe 1/86 Admin Pg. 11
p SECURITY DEPART 1tElfT S4Re84RY OF RESPOt0SIBILITIES Develop and administer security services directed to creating a safe and protected environment for CPU Nuclear employees, property and the public. ML3OR FUteCTIOttS Direct the plant security guard force and surveillance systems and controle including physical security, physical barriers, access requirements, detection aids, communications requirements, security equipment testing and maintenance, response requirements, records and reports involving such activities as:
- Ensure that the nuclear generating stations are adequately protected against acts of sabotage, arson, theft and civil disturbances
- Direction and control of site security forces
- Develop and execute plans and procedures for the physical security of the nuclear stations
- Implement company and MtC rules and regulations
- Screen all non-company employees and contractors for unescorted access to the
- facility
- Provide access control through the use of security surveillance equipment Plan defenses for civil disturbances and demonstrations
- Investigate all security incidents
- Provide liaison to regulatory agencies 1/86 Admin Pg. 12
. ; 3
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DIRECTOR ADMINISTRATION 7fno le8 CLEAR SEQlRITY DIRECTOR
- Mieleon with CRIE Security 7d 00 uhach is roeponsible for escurity at Readarug and Persippany locations j MC2 SEQ 8RITY 7410 Responsible for the supervision of Security Managers et TMI-1. TMI-2 and Dyster Creek. The Security Managere et each of these locatione are roeponsible for
. Policies & Procedures Development .Neintain Knowledge of Current and Compliance Regulations & Resysiremente
. Responsible for Guard Force & .tisioon with Local, State &
Control of Ingrees & Egrees Federal Law Enforcement
. Direct Mejor Investigations Agencies
. Coordinate With Training Depart- .Coordanete with Licensing' ment in Development & Conduct of Department in Properation of Training Programa ";-
-- to K & Other
.Muintain Effective Security Copiaant Governmental System Security Inspections Audite
& Regulatione 1/06 Admin Pg. 13
-4
i i I OPERATIONS AMALYSIS DEPARTIENT j SimesARY OF RESPONSIBILITIES 1 Provide management with an independent assessment of operational efficiency and
- effectiveness, including recommendations designed to improve productivity and reduce
! costs. i ! MAJOR FUNCTIONS i i Conduct operational studies to assess the effectiveness and efficiency of resource usage Report on trends in productivity levels Conduct staffing utilization reviews by measuring organizational workloads and identifying appropriate personnel requirements Assess the productive use of labor Perform special studies to identify improved ways of conducting business. i i i I f j 1/86 Admin Pg. 14
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GPU NUCLEAR C0000UNICATIONS DIVISION SIRGIARY OF RESPONSIBILITIES Generate an understanding of the Company's activities among its public, i.e., public officials, industry, media and regulatory agencies in conjunction with GPU systems communications programs. Develop and manage internal and external communicalions programs. MAJOR FUNCTIONS Media Relations: Coordinate the release of information to the print and electronic media
- Schedule and hold news briefings
- Improve existing media relations by an outreach program Employee Comanunications:
- Keep employees advised on nuclear and system information 'ia special bulletins, house ore,ans, video updates and meetings Provide, train and maintain a qualified staff Implement, when necessary, the ca==anications portion of tha Fm egancy Management Plan Identify issues and engage in advertising campaigns and specific public affairs strategies Establish and improve cosumunications with elected and appointed officials Establish and improve communications with various community groups, i.e. energy advocacy groups, women's groups, medical groups, service clubs and chambers of commerce 1/86 Pg. 1
,-~,
CPU NUCLEAR COISIUNICATIONS DIVISION (continued) Operate speakers bureau and educational program Operate and expand Visitors Center, including tours and briefings ! Operate communications library graphics / art support, photographic support and word processing capabilities , Distribution of written and visual materials for public and employee use (e.g. GPU i Nuclear TODAY and Info / Updates) Establish and maintain plans and schedules, policies, procedures, standards and practices for the Division Develop, gain approval and operate within approved budget, annual and 5 year plans Develop and maintain ef fective consultation and advice with other Divisions to help , assure efficient functioning of GPU Nuclear l 1 i l 1 4 f l 1/86 COMM l Pg. 2
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PUBLIC AFFAIRS DEPARTMENT SISGIARY OF RESPONSIBILITIES . Establish and improve commnunications with elected and appointed of ficials, community groups, to operate a speakers bureau, to operate the Visitors' Center at 1111 and to develop specific public affairs strategies MAJOR FUNCTIONS Establish and improve communications with elected and appointed officials j Establish and improve communications with various cosumnity grr,ups, i.e. energy advocacy groups, women's groups, medical groups, service clubs, chambers of cosmerce 1 Operate speakers bureau to include scheduling, graphics support and training Operate and expand Visitors Center to include tours and bricfings l
- Establish and operate a nuclear energy education program with local schools i
1 1 I i l l i l I I 1/86 1 Comm j Pg. 4 4 l
DIIECIOR , CGIGGANICATIONS N Of 00 i b ~ 1 1 l 1 MApe4GER pgue GER RJBLIC M FAIRS PUBLIC AFFAIRS l IMI E airsi 311o j . Establish and 5eration of . Establish and .%erstaan of leprove Comammi- Speakers Buroeu Improve Communi- Speakere Bureau cataone with to include cations with to include Elected and Ap- Scheduling, Elected and Ap- Scheduling, f pointed Officaala Graphics Sapport pointed Officials Graphics Sapport ,l .Establash and In- and Training . Establish and lo- and Training prove Comminicatione .%erste Visitors' prove Comminicatione . Establish and I wath Various r-mi. Center with Various Communi- operate nuclear ty Croupe, i.e., . Establish and ty Groupe, i.e., energy education Energy Advocacy operate nuclear Energy Advocacy program within Groups, tsuman's energy education lace! achools Croses, Medical program within ! Croupe. Service local schools Clidas, Chambers of Comerce I i I I l i l i 1/86 Comm Pg. 5 i
. ~ r. PUBLIC INFORMATION DEPARTMENT SmeIARY OF RESPONSIBILITIES Maintain media relations, employee communications, coverage of TMI & OC related events, direct the communication portion of the Emergency Management Plan and contract with outside consulting service to identify issues. MMOR PU8ICTIONS Media Relations: Furnish news releases covering TMI and OC events to newspapers, TV and radio stations Schedule and hold news briefings Improve existing media relations by an outreach program Employee e - inications: Keep employees advised on nuclear and system information via special bulletins, house organs and meetings Division coverage of 1MI and OC related events, e.g. ASLB hearings Direct the c-inications and OC portion of the Emergency Management Plan 1/86 comm Pg. 6
. . - - - - _ - _ _ . . . _ _ _ . - - _ . -__ ~ .. _ _ _ . _ _ _ . _ _ _ . .- . - .-. -
O DIE CTOR Cnnaam' CATIONS j _ - _ hk )
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.Esplayee Cemensnicetlano:
l -Esep faployees Advised en j thsclear and System Infoses-tien Via Special Sulletine. . 1 Neune Organe end temotings 1 1 1
. Media Belations:
-Fisrnish tem.o Solenese Covering E & TME Events
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-Schedule end Held teense Briefings
-Iaprove fuisting Media j Relations by en Ekstreach i
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. Division Coverage of E and
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1 i SPECIAL PSDJECTS DEPARTME8Fr
$4 Age 48Y OF RESPOtISIBILITIES Provide support for all comnications projects 8tWOR FUNCTIOGIS Furnish support activities for communications projects / personnel:
Financial, including budgeting Procurement: prepare requisitions and oversee expenditures for all Out capital and outside professional services Management of all c - aications division facilities, information management to operations of c-==ications library Craphics/ art Photographic Word processing Transportation Distribution of uritrea and visual meterials for public and employee use (e.g. CPU helear TODAY and Info / Updates) Personnel administration hiring and salary administration Arrange for aceting rooms and logistical support for briefings, conferences, etc. Contract with consulting services to identify specific public affairs strategies and advertising 1/s6 Comm Pg. 8
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.Distributien of teritten and 7 vieus! Desteriale for Pietic -
l and Eayleyse use (e.g. EFU j ansclear Tim 4V and InfeAspdates) l . Arrange for SInsting Heems and i Legistical Sigpect for Briefings l Conferences, etc. l . Contract with Cannulting ! sorwices I .Propero and Store Information
- into immed Processing Espeapeant l . Prepare and Di= = *==*=
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.Cateleg and Provide Library j Aeference for teritten j 80steriale l .Photogre$ ic Segport
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SammaaY OF RESF00151BILITIES l Responsible for the establishment and implementation of uniform occupational health, i industrial safety, medical, radiological and environmental policies, practices and procedures required to support safe, reliable and efficient operation in accordance with corporate policies and all applicable laws, regulations and licenses. 1 l ItMOR Fugh'.TlettS I i Establish and miintain corporate level policies, procedures, standards and practices relating to occupational health, industrial safety, medical, radiological and j envaroamental activities I
- Provide and maintain a qualified staff
! Provide procedures and administrative controls to develop and implenest the plant ! occupational health, industrial safety, medical, radiological and environmental control programs Provide professional guidance to CPUIl activities in the following areas: l l Radiation protection, radiation dosimetry, radioactive materials, respiratory i protect ion, radiological engineering, AIARA progrees, medical, industrial safety and 1 envaronmental protection and monitoring and environmental permit compliance 1 ) Frovide professional medical, industrial safety, environmental protection and radiation j protection guidance j l Provide administrative and technical guidance applicable to industrial safety, occupational healt h, environmental protection, environmental monitoring and IE' DES 4 I Develop, gain approvat and operate within approved budgets, amasal operating plea and f the multi year strategic plan I Develop and maintain effective comaultation and advice with other divisions to help ! assure efficient tuactioning of CPU liuclear ) Coo:Jinate company activities at Santoa i, 1/s6 R&Ec
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! l & ane EGGICm I
- - - ~ ~~ ~l ASSESSOR - 0.C. 1 -
1 I I _ _ _9CD_ _ _I i l l l l j sanangA AaDIa CGICAL AADIEGGICE IlesSTRIAL SAFETY lease EA stDI CR RADIEGGICE cohtam s CGhihK S & E8AflASSENTE AADtEOGICE CI ECTOR CohTAES DIE CICR DIECIGH CGIITRELS EBClefERING TM-1 TM-2 0.C. DIECIGR Cor. 9100 9 750 92m 94ml 95tB 9700 f e 1/R6 asEC Pg. 2 i
RADIOLOGICAL CONTROLS DEPARTMP.HT, TH1-1 SUlttARY OF RESPONSIBILITIES The THI-1 Radiological Controls Department is responsible for the implementation of the 1 Corporate Radiation Protection Plan. In addition, the department is responsible for monitoring and enforcing the implementation of all radiological control policies and procedures consistent with the requirements of the plan in support of the operation and maintenance of THI-1 MAJOR FUNCTIONS l Control external exposure through the administration of a Dosimetry Program, in j accordance with the As Low As Reasonably Achievable Policy (ALARA) J Control internal expo.sure through the administration of a Respiratory Protection, Bioassay and Whole Botly Counting Program i Control Radioactive Cantamination Control Radioactive Materials Monitor and control Radioactive Effluents Perform reviews of the Radiological Controls Program , Maintain procedures ti2 ensure exposure to workers and the general population is As Low j As Reasonable Achievable (ALARA) i l Support normal plant operation and provide additional support prior to, during and l af ter outages i j Assure corporate compliance with appropriate Radiological Regulations and Licensing ! Requirements Stop work not being accomplished in accordance with appropriate Radiological Controls practices and procedures, when deemed appropriate 1/86 R&EC Pg. 3
r ~. - 01ECIOR RADIE 0GICAL & ENVIRONENTAL CONTROLS 90f G MANAER . e RADIO _0GICAL .
~
CONIROLS IMI-l 91f 0 t(PUiV MANAER RAD 10L OGICAL ,
~
CONIHOLS THI-1 - 9 ,00
~
. Provide Adelnistrative Support l Aliiitl iilSTPiltii-l . Budget Preperation
__,______l RADIOL OGICAL l . Monitor Expenditures l CONTRULS TMI-1 l .Propere Purchase Requisitione l 9100 _l . Review Invoicoe
.Swervlee Clerical Staff I I HAD10L OGICAl RADIE 0GICAL Fl[LD (PERAitfMS ENGlKERING MANAE R THI-l MANAGER TMl-1 9120 3 __
9140
. institute and Maintain Monitoring .Parform Audits and Reviews and Surveillance Programs .Masntain Prucedures
. Control Extern 61 and Internal Exposure . Implement ALARA Program
. Control Contamination .Aeoure Compliance with
. Control Radaoactive Meteriale Nogulatione and License Re-
. Support Plant Operatione and Outages quirements
.laplement Dosimetry Program .Provido Tectriical Guidance in l .lsplement Respiratory Protection, Red Con l
Bioassay & WBC Programe .laplement and Maintain Effluent I l Monitoring Program 1/86 RAEC Pg. 4
~
py - *. RADIOLOGICAL CONTROLS DEPARTMENT, 11ti-2
SUMMARY
OF RESPONSIBILITIES The TH1-2 Radiological Controls Department is responsible for the implementation of the 4 Corporate Radiation Protection Plan. In addition, the department is responsible for monitoring and enforcing the implementation of all radiological control policies and procedures consistent with the requirements of the plan in support of the THI-2 operations, maintenance and recovery effort i MAJOR FUNCTIONS Control external exposure through the conduct of programs to minimize personnel exposure in accordance with the As Low As Reasonably Achievable policy (ALARA) Control internal exposure through the administration of a Respiratory Protection. Bioassay and Whole Body Counting Program , Control radioactive contamination l Control radioactive materials Monitor and control radiactive effluents Perform reviews of the Radiological Controls Program I
- Maintain procedures to ensure exposure to workers and the general population is As Low As Reasonably Achievable (ALARA)
Support normal plant operation and provide extra support prior to, during and af ter outages and during the recovery effort Assure corporate compliance with appropriate Radiological Regulations and Licensing j Requirements l l l l l Y 1/86 R&EC Pa. 5
r .
- RADIOLOGICAL CONTROLS DEPARTMENT, THI (Continued)
Stop work not being accomplished in accordance with appropriate Radiological Controls practices and procedures, when deemed appropriate Train and qualify radiological technicians in Radiological Controls Procedures and techniques in 1MI-2 and qualify radiological technicians in TMI-1. Approve radiological training of others Provide dosimetry program services for THI-1, TMI-2 and Oyster Creek Provide respiratory protection, bioassay and whole body counting services for THI-l and THI-2 Maintain and calibrate all radiological equipment used by the TMI-l and IMI-2 Radiological Controls Department e l I l 1/86 R&EC Pg. 6
D DIE CIDH RADIOLOGICAL & , ENVIRONENTAL CONTROLS 9000 RADim 0GICAL CONTRULS DIE CTOR THI-2 9200 l SENIOR T PRJICil . Prepare Budget l C00RDINATOR l . Monitor Expenditures
-~~~~~~l RAD. CONTROLS l .Propere Purchese Requisitione l l . Review Invoices l_ 9200 _l . Provide Admin. Support i I I HANAGER MANi &ER RADIULUGICAL MANAGER RADIE UGICAL RAD. FIELD TRAINING RADIE 0GICAL lEALTH UPERATIONS MANAGER ENGIKERING 9210 9220 923u 9240
. Provide Dosimetry . institute and Hein- .irain & Quellfy . Perform Audite & Reviewe Program Services tain Monitoring & Technicians . Maintain Procedures for THI-1 & 2 & OC Surveillance Pro- . Approve all Radio- .laplement ALARA Program
. Provide Respiratory grams logical Training of . Assure Compliance with Protection, Bioassay . Control External & Othere in the Areas Regulations & Liconee
& WUC Services for Internal Exposure of Course Content Requirements IMI-l & 2 . Control Contamination Acceptability of . Provide Technical
.Haintain & Cali- . Control Radioactive Instructors and Guidance in Red Con brate Rad. Equip- Material Examinations .leptement and Heintain ment for THI-1 & 2 . Support Plant Opera- . Administer all Erfluer t Monitoring tions & Outages Radiological Quali- Programe fication Examina- . implement and Heintain tione looshield Program I 1/86
, RAEC l Pg. 7
THREE MILE ISLAND INDUSTRIAL SAFETY AND RADIOlDCICAL ASSESSMENT DEPARTMENT
SUMMARY
OF RESPONSIBILITIES The Three Mile Island'(TMI) Industrial Safety and Radiological Assessment Department performs independent acalysis of the implementation of the industrial safety and radiological controls programs and practices at Three Mile Island MAJOR FUNCTIONS Conduct frequent tours in areas whe re work is being performed Review compliance with Federal Regulations, license requiresients, industrial safety and ' radiological control procedures ' Prepare periodic industrial safety and radiological assessment reports for management Review radiological work practices for ALAMA considerations i Review work practices for OSHA considerations Stop work not being accomplished in accordance with appropriate Industrial Safety and Radiological Controls practices and procedures, when deemed appropriate 1/86 R&EC Pg. 8
f) DIlE CIOR RADIE 0GICAL & EWIRuNefNIAL CONTROLS 90f D IMI IfGISil:IAL SAFEIV A#O RADIE 0GICAL AST SSOR 9610 i
.(berve Areas Whero Work le in Progress
. Review Compliance with Federal
! Regulations and License Requirements
. Prepare Radiological Assessment Reports 1
. Review Radiological Work Practices For ALARA Considerations
. Review Compliance with OSHA Regulations
- and Requirements
. Review the Work Practices for OSHA Considerations j
l 1 l l .I 1/86 RKC 1 Pg. 9
Q. OYSTER CREEK INDUSTRIAL SAFETY AND RADIO 14CICAL ASSESSMENT DEPARTMENT SL4etARY OF RESPONSIBILITIES The Oyster Creek (DC) Industrial Safety and Radiological Assessment Department performs independent analysis of the implementation of the Industrial Safety and Radiological
) Controls programs and practices at Oyster Creek MAJOR FUNCTIONS Conduct frequent tours in areas where work is being performed Review compliance with Federal Regulations, license requirements, industrial safety and radiological control procedures Prepare periodic industrial safety and radiological assessment reports for management Review radiological work practices for ALARA considerations Review work practices for OSHA considerations Stop work not being accomplished in accordance with appropriate Industrial Safety and
- Radiological Control practices and procedures, when deemed appropriate i
l l 1/86 R&EC Pg. 10
D. . DIECIOR RADI(LUCICAL & ENWIRG#fhiAL CONTROLS 90IO (E IMUSil!!AL SMEIV AM) RADi(LOGICAL ASSE SSOR 9620
.(berve Areas Where Work is in Progress
. Review Compliance with Feders!
Regulatione and License Requirements
.Propero Radiological Assessment i Reports
. Review Radiological Work Practices for ALARA Consideratione
. Review Compliance with OSHA Regulatiorw and Requiremente
. Review the Work Practices for OSHA Considerations i
l l 1/86 R&EC Pg. Il
g, . . RADIOLOGICAL CONTROLS DEPARTMENT AT OYSTER CREEK .
SUMMARY
OF RESPONSIBILITIES The Oyster Creek Radiological Controls Department is responsible for the implementation of the Corporate Radiation Protection Plan. In addition, the department is responsible for monitoring and enforcing the implementation of all Radiological Control policies and procedures consistent with the requirements of the plan in support of the operation and maintenance of Oyster Creek MAJOR FUNCTIONS j Control external exposure through the administration of a Dosimetry Program, in 4 accordance with the As Low As Reasonably Achievable Policy (ALARA) Control internal exposure through administration of a Respiratory Protection, Bioassay and Whole Body Counting Program Control radioactive contamination j Control radioactive materials , Monitor radioactive effluents Perform reviews of the Radiological Controls Program Maintain procedures to ensure exposure to workers and the general population is As Low As Reasonable Achievable (ALARA) i Support normal plant operation and provide extra support prior to, during and af ter j outages Assure corporate compliance with appropriate radiological regulations and licensing requirements l l 1/86 R&EC Pg. 12
r . I RADIOLOGICAL CONTROLS DEPARTMENT AT OYSTER CREEK - (Continued) Stop work not being accomplished in accordance with appropriate Radiological Controls practices ar.d procedures, when deemed appropriate i Train and qualify radiological control technicians in radiological control procedures j and techniques. Approve radiological training of others - Provide respiratory protection, bloassay and whole body counting services for Oyster Creek
, Maintain and calibrate all radiological equipment used by the Radiological Controls Department 1
e i I i i 1/86 R&EC Pg. 13 ,
0164CIOR RADIOL OGICAL & ENVIRONWNTAL CONTRES 90fo RA01a 0GICAL CONIRE S DIRECTOR
- OYSTER CREEK 9300 DEPUTY DlHECTOR RADil10GICAL CONTRES DYSIER CREEK 9300 l~ E!E R 0 IG CAL ~l . Dept. Admin. Duties
-~~---
l CONIRE S l . Budget Preparation
, 7 ADMIN. E l .Expendituto Monitoring l l . Prepare Purchase Requisitione l_ 9300 _l . Review Invoices l I I l RAull1 0GICAL RADIE UGICAL 3)PERVISOR HEAT TH FIELD (FS. RADIOL OGICAL l RADIE UGICAL ENGlW ERING MNAER MANAER TRAINING MANATR
- T E DC OC 9310 9320 9330 9340
, .!mplement Ibsimetry . Institute and . Train = Qualify . Perform Audits & Program Maintain Monitoring Technicians Reviews
.Provioe Respiratory and Surveillance . Approve all Radio- . Maintain Procedures Protection, Blossay Programs logical Training . implement ALARA Program
& WDC Program . Control External and of Others in the Areas . Assure Compliance j Services Internal Exposure of Course Content Ac- with hegulatione l . Maintain & Call- . Control Contamination ceptability of In- a ticonee Require-I brate Radiologi- . Control Red Materials structors and Examina- mente cal Equipment . Support Plant Operation . Administer all Radio- . Provide Technical and Outages logical Qualification Guidance in Red Con Examinations I/06 RAFC Pg. 14
1 . . r, '
- i
.,i SAFETY AND ENVIRONMENTAL COtrTROLS DEPARTMENT SINGIARY OF RESPONSIBILITIES j 1he Satety and Environmental Controls Department is responsible for all industrial safety and environmental matters at Oyster Creek and Three Mile Island. This is accomplished through the implementation of all monitoring and study requirements of i USNMC, USEPA, NJDEP, PaDER, OSHA and NIOSH, as contained in the Environmental Technical i Specifications, the National Pollutant Discharge Elimination System permits or other t company commitments and/or policies and procedures l i' MAJOR FUNCTIONS l Perforu Radiological Environmental Monitoring Programs to assess impact of radiological
- releases on surrounding populations i
Operate and maintain the meteorological towers i i i i Assess the impact of plant operation on terrestrial and aquatic life i + Monitor depth of water in adjacent rivers and bays to ensure sufficient cooling water and determine if navigability has been affected by station operation Conduct other environmental monitoring and reporting and assure corporate compliance j with appropriate Environmental Regulations and Licensing requirements 1 l Support corporate attorneys in civil and administrative environmental hearings i Implement Industrial Safety Systems and regulations; perform surveys and approve safety equipment, policies, procedures and implementation for compliance with OSHA and NIOSH ! Perform injury and accident reporting; oversee safety training; maintain tool and l safety equipment manual; audit and investigate injuries, accidents and determine corrective action l 1/86 R&EC Pg. 15
r ' l I DIR CIOR RADIOLOGICAL & EWIRONENiAL CONIROL5 90f0 l IM)uSIRIAL SAFEIV & E MIRONE NIAL CONikES .Dowelop & Maintain Emergency Dffeite DIRECTOR Does Projection Programe 9400 . Provide Computer Support Services 1 f CON 5tiANI 'l . Coordinate Computer Activities lRADIR OGICAL & l Between RKC Divleion & Information
- - - ~ ~ -lEWIRONENTAL l Services l CONTROLS l . Coordinate Computer Hardware Requiremente l_ _ .243L _ __l within RKC
. Provide Technical Support to RK C 4 I I
) nueAGER MM64ER EWIROMENTAL MAM ER ENWIRONENTAL E WIRONE NTAL CONTROLS IM)USiRIAL SKETY ll CONIRULS CONINOL S MANAE R & KALTH ! E THE C0froRATE 9410 9420 9430 9440
. Perform Environmental . Perform Environmental . Assume Corporate Con- . Develop Policies & Procedures Monitoring Programe Denitoring Programs pliance with Regule- to Comply with OSHA & NIOSH
. Operate Meteorological .uperate Meteorological tions & Liconee Re- . Implement Safety Programe Towere Towere quiremente
, . Develop Safety Training
.Aseems Environmental .Assese Environmental . Perform Corporate Env. Programe & Compliance lupact of Plant lopect of Plant Analyste & Review '
with Saoe Operation Operation . Provide Meterological . Perform Safe Working Conditione
. Coordinate Overall Guidance Surveys GPUE Activities Re- . Coordinate Activities .Dowelop Injury Reporting Pro-garding Sexton Between Tech Functione cedures
. Provide Liaison Be- A Environmental Con- . Investigate Injuries & In-tween GPU E & SK C trole plement Corrective Actione
. Conduct Necessary . Coordinate Inter . Maintain Tool & Safety 1 Surveys & Monitoring Company Environmental Equipment Manuel I
at Saxton Activities
. Institute & Maintain CPU E Right to Know Program Note: GPUDC carries out wurk on Sexton as mutually agreed upon by j SEC and GPUE 1/86 RKC 1
Pg. 16
I r, CORPORATE RADIO 1DCICAL ENGINEERING DEPAR1 MENT SUteIARY OF RESPONSIBILITIES 1 l The Corporate Radiological Engineering Department is responsible for radiological i oversight of proposed plant modifications to assure implementation of the ALARA I philosophy and acceptable radiological practices and the medical / legal aspects of i radiation exposure and radiological effects i MAJOR FUNCTIONS ALARA reviews of proposed plant modifications Assist in the performance of radiological audits at TMI or Oyster Creek, as requested i Provide radiological engineering support to other divisions of the Nuclear Corporation, j as required
; Provide radiological engineering support to the Radiological Controls Departments at TMI or Oyster Creek, as may be needed from time tp time Provide guidance to the Division Director and others in the medical / legal aspects of radiation exposure and radiological effects 1
Provide oversight on all radiological records and their disposition within CPUN 4 I l 1
)
1/86 R&EC Pg. I7
DIECIDH RADia 0GICAL & EMIRONENTAL CONTRES 9000 C0FLRATE RADIE UCICAL ENGIEERIE. 9500
.Perfore ALARA Reviews
. Assist in Radiological Audits
. Perform Radiological Engineering Assistence to (PUN Diviolons
. Perform Radiological Engineering Support to IM & UC Rrdiological Controls Departments
.Nanage the Legel/Nedical Aspecte l of the Radiological Progres 1
I l i l l I l t j 1/86 RafC Pg. 18
m - MEDICAL DEPARTMENT SUletARY OF RESPONSIBILITIES 1he Medical Department is responsible for the direction of the CPU Nuclear Medical l Program; this includes direction of contract physicians and CPU Nuclear medical personnel, as well as provision of professional medical guidance and participation in radiological mattera MAJOR FUNCTIONS Recommend sound medical policies for the conduct of business by CPU Nuclear Corporation Direct and implement the CPU Nuclear Medi:a1 Program and certify the professional qualifications of the medical staff Provide medical guidance to the divisio<a directors in the medical aspects of radiation exposure and other occupational health hazards Establish and maintain technically clear and concise medical records i Establish or recommend actions needed to provide a medically safe working environment Monitor all occupational, work-related health proble:ss at the work site and implement . programs along with others, as appropriate, which aim at their minimization 1 l 1/86 R&EC Pg. 19
DIECTOR RADi(LOGICAL & EWIRONENTAL CONTROLS 90re E DICAL DIRECTOR 9700
. Implement Medical Program and Policies
. Provide Guldence in Radiation Exposure Mettere and Other Occupatiorul Health Hazarde
. Maintain Medical Recorda
. Ensure Medically Safe Working Environment i
l l i 1/86 R&EC Pg. 20
- p. ~ -
I l ! CPU NUCLEAR I MAINTENANCE, CONSTRUCTION & FACILITIES DIVISION i l l
SUMMARY
OF RESPONSIBILITIES ' Establish and implement uniform policies, practices and procedures for managing, planning and conducting all maintenance, repair, facilities, transportarion and construction activities in accordance with corporate policies and all applicable laws, regulations and licenses and technical requirements Accomplish all plant modifications, maintenance, repair, and construction activities as assigned in accordance with corporate policies and all applicable laws, regulations, licenses and technical requirements 1 Maintain the Forked River construction site 4 MAJOR FUNCTIONS Evaluate and assure that maintenance activities at THI-l and Oyster Creek are being l performed in accordance with corporate policies, procedures and good maintenance practaces Provide and maintain a qualified staff Establish and maintain the necessary corporate level maintenance and construction procedures, standards and practices for the performance of maintenance and construction activities i Develop, issue and report progress against integrated schedules for work at TMI and l Oyster Creek consistent with established cardinal dates and the long range plan 1 Plan, schedule and direct plant modifications, plant construction projects and major l and specialized maintenance jobs at TMI-l and Oyster Creek, including those special maintenance and construction activities involved in planned and forced outages j l i 1/86 MCF l Pg. 1 i I
p . . Develop, gain approval, and operate division within approved annual budget, annual operating plan, and the multi year strategic plan Plan, schedule and direct activities required to provide transportation services, equipment and telecommmunications 4 i Represent CPUN on Company and site-wide labor relations matters with owner companies i Develop space allocation within non plant facilities with the concurrence of the plant director Manage assigned shops, calibration facilities, tool rooms and maintenance equipment Develop and maintain ef fe ctive consultation and advice with other Divisions to help assure efficient runctioling of CPU Nuclear Prepare, recommend and <.ontrol capital budget for facilities and transportation i 1 ) i ), l l I 1/86 I MCF l Pg. 2
,e. ~ ~
l MINTENMCE, CONSTRICTION & FACILITIES DIVISION 4 0FFICE OF Tif PK SIDENT 1000 I D1 K CTOR MINTEMEE CONSilGJCTION & . i FACILillES A000 e l l l TrEC. PRadIS ________l seCLEAR l l l oIRECTOR I I _ _AL100_ _. _I i i I I I I I I MMER EF DCF PNUQJCilON MNAGER EF EF ADNIN. EF Dil FCIOR ~ EF DIKCIOR -fEJ DilECI(iii PL ANNING DIRECTOR E TH00S & SUPPORT DER. FACILITIES OVSIER CREEK TM-1 PROCFDJK S A010 A020 AD 30 A040 A050 A100 A200 l l l l l l 1/a6 EF Pg. 3
- s. .
MAINTENANCE, CONSTRUCTION AND , FACILITIES - OYSTER CREEK SUtetARY OF RESPONSIBILITIES Implement policies, practices and procedures for all maintenance, repair and construction activities for the Oyster Creek Nuclear Generating Station ir accordance with corporate policies and direction, as well as all applicable laws, regulations and license and technical requirements Direct the conduct of assigned plant modifications, repair and construction activities and accomplish major and specialized maintenance work for the Gyster Creek Nuclear ! Generating Station in accordance with corporate policies and direction, as well as all applicable laws, regulations and licenses and technical requirements 1 i MAJOR FUNCTIONS Provide, manage and direct required departmental support in the following functional areas: A. Planning - Workload and Control, Planning and Scheduling, Estimating and Cost ' Analysis l B. Production - Project Engineering, Production Work and Materials j C. Technical Support - Welding, Turbine, Valves / Pumps, Methods / Practices and Documentation D. Administrative Support - Personnel and Management Assistance, Contractor Services l E. Facilit ies - Transportat ion, Facilities, Maintenance and Services, Tools and l Equipment 4 1 l 'l/86 l MCF i Pg. 4
.R 1
DilECIOR MAINTENAEE, CONSlitJCilDN & FACILITIES Aoro i l l MAINil NAEE , CONSiltACTION & FACILillES DIRECTOR 0.C. Alf 0 l~ MINIEMAEE7 ~l i
- l CONSTRUCTION & l
~ ~ - - - - - ~ ~lFAcit lilES GliAGE l lMANAG R - O. C. l l_ _ _A112 _ _ _l M4h GH MAMEEN M4ER EF 4OMIN. Malt GER
! KF PLANNING KF PROG)CTION E F TECHNICIAL SJPPORT MANAER EF FACILITIES
- 0.C. 0.C. SJPPORT 0.C. 0.C.
i 0.C. Alto Al20 AIM A140 A150 i
. Work Planning . Project Manageesnt . Welding . Personnel . Plant Facilities
. Work Inventory . Vendor r".er- , - .t . Turbine . Budget Heintenance j . Work Schedulang .Crafte Management . Auxiliaries, . Cost .fquipment I . Job Plannang .Heteriale Electrical . Training Coordin- .Toole
. Job Scheduling . Processes ation .irensportation
. Job fetimating .Qualificatione .0ffice Servicae . Plant Facilities
.Materiale Planning . Records .Emposure Control Services
. Cost Analysis .Ducumentation .ADP leplementation . Forked River Site
. Schedule Assess- .Methode .!SM laplementation Maintenance ment . Procedures . Contractor Services
.Modafication Core Management trol 1/86 Kr Pg. 5
- r. .
131NTENANCE, CONSTRUCTION AND FACILITIES - TML-1 S4406ARY OF RESPONSIBILITIES Implement policies, practices and procedures for all maintenance, repair and construction activities for the Three Mile Island Unit 1 Nuclear Generating Station in
' accordance with corporate policies and direction, as well as all applicable laws, regulations and license and technical requirements I
Direct the conduct of assigned plant modifications, repair and construction activities and accomplish major and specialized maintenance work for the Three Mile Island Unit 1 Nuclear Generating Station in accordance with corporate policies and direction, as well as all applicable laws, regulations and licenses and technical requirements 4 i MMOR FUNCTIONS i
! Provide, manage and direct required departmental support in the following functional areas:
A. Planning - Workload and Control, Planning and Scheduling, Estimating and Cost Analysis B. Production - Project Engineering, Production Work and Materials C. Technical Support - Welding, Turbine, Valves / Pumps, Methods / Practices and l i Documentation D. Administrative Support - Personnel and Management Assistance, Contractor Services E. Facilities - Transportation, Facilities, Maintenance and Services. Tools and Equipment I I 1/86 MCF Pg. 6
- p.
- DilECIOR MAINTENAEE, CONSilaJCTION &
FACitlTIES 4000 MAINTL NAEE , Cf>ISTRfCTION & FACILITIES DillECTOR I TMI-1 ' A200 l dlNTEii48EE7 ~l l CONSTiluCTION & I
- - - - - - - lFACILITIES BliAKl lMANAE R - TMI-l i 1._ A202 _ _l l 1 I
, MANAGER MAieAER MANAE R ICFiOMIN. MAM ER ) KF PL ANNING KF PR000CI10N KF TECHNICIAL fiUPPORT MANAER ICF FACILITIES j iMI-l IMI-l SJPPORT TML-1 TMI-1 i IMI-1 A210 A220 A230 A240 A250
. Work Planning . Project h =-; .t . Welding . Personnel . Plant facilities 1 . Work Inventory . Vendor Management . Turbine . Budget Maintenance
. Work Schedulitug .Crofte Management .Auxilleries, . Coat . Equipment.
. Job Planning .Mutoriale Electrical . Training Coordin- . Tools i .Jub Schedulang . Processes stion .irensportation
! . Job Estiestarw; .Quellficatione .0ffice Services . Plant Facilities
! .Materiale Planning .Recorde . Exposure Control Services
- . Cost Analyess . Documentation .ADP leptementeLion . Forked River Site
. Schedule Assees- .Methode .191 leptementation Maintenance i ment . Procedures . Contractor Services
.Mudificetion Con- Management
! tml i
I/86 WF Pg. 7 i
~
P. PLA8BlING DEPARTMENT SlSetARY OF RESPONSIBILITIES Plan, implement and manage all functional responsibilities of the Maintenance, Construction & Facilities Division in the Planning area i Provide and manage appropriate oversight / monitoring efforts for each site to assure that corporate policies, practices and procedures for all maintenance, repair and I construction activities in the Planning area are accomplished, as prescribed MMOR FUNCTIONS l Manage the workload inventory by planning, scheduling and assignment within the Division and appropriate interface with other Divisions i i Manage the authorized modification program Manage all assigned job planning preparation and scheduling Manage all schedule assessment efforts j! Coordinate job estimating and cost analysis requirements i j Develop and manage corporate integrated schedules l Provide division support in the ADP and IMS areas and interface with nther j divisions / departments responsible for providing those services I i 1 i 1/86 i MCF Pg. 8
- v 0
h A ) 5W l.E
*Em
~
( 5- ~ Ww$wag E5 w
!=$
Egd o j 150 "v u
*~
g-w w l 5 l e
O . PRODUCT 1001 DEPARTMENT l l SIRel&RY OF RESPOllSIBILITIES , Plan, implement and manage all functional responsibilities of the Maintenance, Construction and Facilities Division in the Production area i t Provide and manage appropriate oversight / monitoring efforts for esch site to assure i that corporate policies, practices and procedures for all maintenance, repair and construction activities in the Production area are accomplished, as prescribed MAJOR FUllCTIOllS 1 Coordinate Project Engineering efforts, as directed Manage and direct the Prcduction workforce - contractors, vendors and company personnel l Represent GPUNC on Company and site-wide labor relations matters with owner companies l I I 4 4 I, O I l 1/86 NCF Pg. 10 I
b DilECTOR MINTENAEE,
- CONSiltlCTION &
FACILITIES j aar o t I i . i t M INTI. NAE E CONSiltlCTION & FACILITIES Pfl000CTION 1 DillECT0ft ! A020 i 4 1 4 4 i i s i l l 2 l 1 I i i f i 1 1/86 WF Pg. 11 1, I
- 1
?
, m
~
p - - - TECHNICAL SUPPORT DEPARTMENT SUtStARY OF RESPONSIBILITIES ' Plan, implement and manage all functional responsibilities of the Maintenance, Construction and Facilities Division in the Methods and Procedures Technical Support area Provide and manage appropriate oversight / monitoring efforts for each site to assure that corporate policies, practices and procedures for all maintenance, repair and -'j i construction activities in the Methods and Procedures arn! Technical Support area are j accomplished, as prescribed 1 MMOR FUNCTIONS Provide technical support to the Division, as appropriate . Develop and manage various programa for improvement which are assigned, such as the reliability program, experience transfer program and equipment utilization program i. Develop, promulgate and audit generic technical methods and procedures required by the Division Manage and direct preparation of technical processes and instructions required by the ' Division - Manage the program related to construction / maintenance records, qualification, documentation and document controls , j i l l ' 1/86 MCF Pg. 12
A
- e DI ECIOR MINTENAEE, CONSTRACI10N &
FACIllilES AIN G 1 i l
- 1 NANAER MINTENAEE 1 CONSTRACTION &
FACILITIES ETHODS & PROCEGIES i, A030 , 4 l 1 l t 1 l 1 I i. r 1/86 KF Pg. 13
D-ADetINISTRATIVE SUPPORT DEPARTDENT SUlelARY OF RESPONSIBILITIES 4 Plan, implement and manage all functional responsibilities of the Maintenance, Construction and Facilities Division in the Administrative Support area Provide and manage appropriate oversight / monitoring efforts for each site to assure that corporate policies, practices and procedures for all maintenance, repair and , construction activities in the Administrative Support area are accomplished, as I prescribed l MAJOR FUs... IONS Manage the Division's efforts in budget and cost control activities Coordinate the Division's training requirements and interface with the Nuclear Assurance Division in the training area Manage and direct various improvement programs related to personnel Provide Division support in the personnel area 1 Manage and direct the division's administrative policies, instructions and notices r program 1 I l l 1/86 MCP Pg. 14 l i
DI KCTOR MAINTEleMCE, CONSTiWCTION & FACILITIES A000 MAINil.NA8CE CONSilWCTION & l, FACILITIES AD0 TIN. 4 SNPORT MANAER ADAD ' i 6 l i 4 i l. i l i l i i i l 1/86 1 ICF i Pg. 15 1 I
- p. -
FACILITIES DEPARTHENT 1
SUMMARY
OF RESPONSIBILITIES Plan, schedule and direct all activities related to the Provision of Facilities Management i Provide and manage appropriate oversight / monitoring efforts for each site to assure that corporate policies, practices and procedures for all maintenance, repair and construction activities in the Facilities and Equipment area are accomplished, as prescribed
! MAJOR FUNCTIONS Manage and direct activities related to tools, equipment, materials and shops Manage and direct activities related to Site / Corporate Facilities Management Manage the Contractor Services Manage and direct the Corporate Transportation requirements t.
l l i 1/86 NCF
, Pg. 16
+ . . . . , r
- j DilECTOR MINTElWWCE, i CONSTN)CTION &
j FACILITIES A000 ! I i l I ! MINTENMCE , CONSilDCTION & FACILITIES . FAnlLITIES DillECiolt i i A050 i 1 l l i i i i i I i l I i i I I j 1/86 9CF Pg. 17 l
i GPU NUCLEAR COMPTROLLER DIVISION SIRet&RY OF RESPONSIBILITIES Oversee the development, implementation and adherence to financial procedures and , financial control systems for safeguarding the assets of CPU Nuclear and Owners Oversee the development, implementation and adherence to the data processing information system Interpret state and federal financial regulations, generally accepted accounting
, principles and tax legislation, to comply fully and to the best interests of CPU l
Nuclear and Owners MMOR FUNCTIONS Develop, implement and control financial and accounting systems i . i Provide and maintain a qualified staff I Coordinate internal and external financial audits and resolve recommendations Develop and assure implementation of Corporate internal controls and financial policies and procedures l Determine state tax liabilities and perform special tax analyses Direct and coordinate all corporate wide budgets and cost analyses functions i Report expenditures against capital and O&M budgets and compare them with work progress reported by the responsible divisions. Analyze and report the results on a uniform basis on a company, plant and division basis Provide forecasts, schedules, cost estimates, analysis and evaluations for optimum utilization of corporate financial resources Provide for Nuclear Corporation computer equipment, system support, training, j distribution and use of end user oriented products and time sharing capabilities, excluding all computer equipment and services associated with the GPU Energy Management System, which includes all Dispatch related facilities and power plant process control computers
!/86 COMP Po. I
CPU M3 CLEAR
- COMPTROLIER DIVISION (continued) i j
Administer project plans and schedules, coordinate selection, design and implementation of computer systems hardware and sof tware through formal liaison with CPUSC Information Services Design, develop and implement systems and procedures in support of office systems ! technologies, including selection of hardware and sof tware Establish and maintain plans and schedules, policies, procedures, standards and practices for the Division Develop, gain approval and operate within approved annual budget, annual operating plan and the multi year strategic plan ! Develop and maintain effective consultation and advice with other Divisions to help j assure efficient functioning of CPU Nuclear i , i I i l 4 s i i 1 1 f l 1/86 1 COMP l Pg. 2 i
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i B i ( I S R T E O A CT 1 6F. 8 0
/ 0 I C I MI C0 R
ORE 87 KED I I F B ( C L A S T I I 0 I NKY A T A LI h S 0 S N A I I N S F A S A F B ( L G C A N I I T I N ETN0 A A J 1 1 d B T NGR E S I C I S I FC E S A I H R S V T T E A I N L D F E L O D O 0 R I R 0
. E ES I D
L C F E E I E 0 f R F F P 0 C T 0 F D E I C L M R AT 3 EI S3 ImEE1 UNI A C B MIF VR . E L C. R A 0 EI S2 A EE 3 INA A NI CE U MI V F R E R AS L IA EIEIEC 0 1 e A V 0 U MI NR E B F S i ! l 1 ii , i!J l )1
[ *
- i FINANCIAL SERVICES s i SU!stARY OF RESPONSIBILITIES Develop, coordinate and administer financial activities at the Oyster Creek and Three Mile Island Nuclear Generating Stations HMOR FUNCTIONS
.i Analyze expenditures, manage and process Contract invoices . Oversee COMEC data flow and error correction resolutions and the audits of working fund accounts Maintain the moveable asset inventory system and review for completion unitization process reports. Perform periodic field inventories of physical assets Interface with Information Services to maintain efficiency and effectiveness of site computer systems
} j Interface with outside agencies and organizations, such as NRC, State Commissions or
, audit groups and, as representative in major site contract negotiations and bid l openings / evaluations l
Ensure compliance and provide interpretation and resolutions for Financial Policies and Procedures throughout the site , 1 l i I e 1/86 COMP Pg. 4 l
p . . i i 4 CODFTRE LE R B000 i . l MANAER j FINA8CIAL ERVICES j 8010
- . Development. Coordination and i Administration of Site Financial l Activities
{ -Analysis of Expenditurae [- j -Management & Processing of Contract Invoices ! -Review of Completion Reporte j for Unitization Process
-Periodic Field Inventory of j Physical Assets
-Maintenance of Moveable Asset
! Inventory Systes l -Interface with Information
- Services
! -COWC Data Flow & Error Correction Resolution ! -Audit of Working Fund l Accounte l i 1/86 CupF Pg. 5 I
A
- ASSISTANT COMPTROLLER - FIMANCIAL ACCOUNTING DEPART 3ENT SUIGGARY OF RESPONSIBILITIES Direct and coordinate all functions of the Plant Accounting, General Accounting aad Regulatory Accounting Departments. Primary responsibilities include developing, implementing and maintaining the internal control policies and procedures, books of account, accounts payable, accounts receivable and financial records of GPU helear; contributing to rate case management, interpretation of tax law, tax analysis, maintaining and analyzing records of change in property value and effectively managing the corporate assets MAJOR FUNCTIOES Direct the management and maintenance of financial records of CPUN Control the payment of corporate bills through timely and accurate administration of accounts payable Oversee the accurate preparation of financial reports, special financial analyses and associated studies Develop and submit billings to Owners and outside organizations and maintain and report TMI-2 Funding Status / Process Ensure that receivables are collected in a timely manner Direct the maintenance of the financial records of the assets of GPU helear, including the unitization of assets in accordance with regulatory requirements Control ef fective accounting system through directing and coordinating the accounting ,
functions, establishing and implementing financial policy, procedure and monitoring ' financial controls Interp ret state and federal regulations, generally accepted principles and tax legislation to comply accurately to the best advantage of the Company with such regulation and legislation and its continual changes i 1/86 j COMP l Pg. 6
CDeeIROLtER E000 1, ASST. CaseTR(ITER flNA8CIAL ACCIENilpC 8101
# ewe E R ftWe ER peut ER E lfRAL CONSiltJCTION K QJLATORY ACCIDNTIE ACCGJNTING ACCGjNTING 1 Bill B210 B310
. Determination of Appro- . Control, Maintenance & Reporting . Interpretation of Regulations j priate Accommt Classi- of Construction / Retirement Nork and Guidelines Issued by l ficatione According to in Progress Accounting Profession & Aepletory i
FEIC Code of Accounts . Coordination of Unitizing Plant Agencies
. Maintenance of Bouks of Assets in Accordance with . Development and Maintenance of Account Regulatory Requirements Financial Policy and Procedure
.Menegament & Processing .Dowelopment and Maintenance Manuals of Invoices and Empense of Property Records .Rev iew/Rev io iorVEnhancement/lep le-Reporte . Internal Financial Reporting montation of Divleian Internal
.0verseeing Accrual Process of Various Capital Coets Controle
.Develogment and Stamittel . Conducting Physical In- . Monitoring of Compliance with of Billings to theners ventories of Plant Assete Company Internal Controle
. Development and Stemattal . Coordination and Sipport of of Billings to Outside Internel and External Audite Organuations . Monitoring of Compliance with
. Maintenance & Reporting of Audit Recommendations iMI-2 Funding Status / Process . Computation of Tau Liabilities l . Maintain and Report on Status and Other Special Tax Analyses l of Accomets Receivable . Development of External Financial Reports j . Performance of Special Financial Analyses
- and Studies I . Coordination of Comptroller's LOSA Review 1/86 1
CDee 2 Pg. 7 4
O ASSISTANT COMPTROLLER - FIM&MCIA1. AMALYSIS DEPARTIENT S44884RY OF RESPONSIBILITIES Primary responsibilities include establishing and monitoring the budgeting process, providing financial analysis and resource planning, the review and assessment of l; economic evaluations and assurance of asset recovery and installation and I administration of the work order / expenditure control management information system (COMEC) and the Corporate Budget System (CBS). Directs and coordinates all functions of the Budget & Cost Analysis, Financial Analysis & Resource Planning, Asset Economics
& Recovery and Financial Systems Departments i M& JOE FUNCTIONS l Direct and coordinate all functions of budget and cost analyses on a corporate-wide basis. Regularly monitor and report progress and expenditures against capital and O&M budgets, associated work plans and provide analysis for corporate functions and plant l operations I
Provide long-term financial planning, forecasts, schedules, cost estimates, analysis and evaluations for optimum utilization of corporate resources ! Overall assessment of financial and resource data to optimize utilization of Company ' resources j Oversee the preparation, development and coordination of Rate Case information for CPUN l and the performance of special economic analyses and projects 1 j Coordinates the implementation, operation and maintenance of the COMEC and CBS systems in order to ensure the availability of timely, accurate and pertinent reports for management decision making Provides resource planning and reviews and assures economic evaluations and asset recovery analyses are performed to appropriately evaluate capital investment proposals
- and alternatives i
,l 1 1/86 COMP , Pg. 8 j i
s ( - ' COWTRELER BIOD l 4
! ASSISTANT COWTROLLER FINMCIAL ANALYSIS Bd OO l
l l l NueAElt BJ0GEI ER.-F NMC] AL ER.-ASSE I nut ER CEM)INATOR
& COST ANALYSIS ANALYSIS & K- ECONOMICS & FINMCIAL COEC II SGJICE PL ANNIE KCOWERY SYSTEMS
! B51D B610 B630 8650 B651
. Reporting of Budget .0verall Aseeeement of . Review of Proposed . Coordination of Dwerall l Performance Financial & Resource Data Capital Expenditures Corp. Budget System /COEC l
. Coordination & Admini- to (htimize Utilization of .Nonitoring of Leases theretione otration of Corporate Company Resources and Performance of .Nonitoring of Effectivenees
& Diviolon Budgete . Preparation, Development lease vs. Omn Analysee end Utilization of Various
. Coordination & Review & Coordination of Rate Ceee . Performance of Special feeder Systems /Sab-Systems of Projecte Information for GPUN Economic Analyses & For Interface with CIBfC +
. Administration of Work . Design, Development & projects & Corp. Budget System i
Authorization Systees hintenance of CPUN Coat . Performance of Depre- .Neintenance of C0K C Coding
. Development of Quer- Henpower Data Base cistion Analysee Systems & Corp. Budget System j terly Forecaste . Design Development & Pre- Mark Breakdown Structure
. Reporting of Dwertime paration of Corporate Re- . Development. Maintenance &
. Development & Mainton- ports on Cost & knpower Initiation of Education for ance of Budget Informa- financial Systems tion Systems . Provide Timely, Usable Manage-i ment Level Coot Information Through Enhancement of Existing Financial Systems & Development -
{ of New Applications l I j 1/86 l C0w Pg. 9
o - - - , i i INFORM &TIot! SERVICES DIRECTOR SINGIARY OF RESPOtlSIBILITIES i Direct the Information Services function of the company through formal liaison with the CPUSC Information Services Division. Provide direct support to individuals or functions in situations where various types of local data processing services are required, with the intent to expedite and enhance the overall level of data processing service to the GPU System MAJOR PUNCTIONS
- Define the long-short-range information requirements to ensure the most effective I
cost / benefit return on data processing resources , l l Participate in and evaluate the economic justification related to hardware, software { and associated services requirements Administer data base technology within the Nuclear Corporation, coordinate the ! selection, design, implementation and development of computer system sof tware and
- techniques, excluding all computer equipment and services associated with the CPU Energy Management Systems, including all Dispatch related facilities and power plant $
, and process control computers and provide specialised services to maximize technical effectiveness i Design, develop and implement automated office systems and procedures in support of f'
- of fice systems technologies, including selection of hardware and sof tware i
Administer GPUN's computerized equipment and connunications network, excluding all j computer equipment and services associated with the CPU Energy Management Systems, j i including all Dispatch-related facilities and power plant and process control computere I
- Evaluate and prioritize reauests for services through actively interfacing with i management within CPU Nuclear and CPU System '
] Provide CPU IS interface in the control of projects, programs, the development of , systems and support of computer applications within the Nuclear Corporation, excluding '! i all computer equipment and services associated with the CPU Energy Management Systems,
- ancluding all Dispatch-related facilities and power plant and process control computers
-l l !
j INRMtMATION SERVICES DIRECTOR - (continued)
m t Cute TRalf'R 8000 i } .< s 1 e IWORet4T10N SERVIES
. DIRECTOR B701 i
I l l st4NAGE R DA A 0FF E APPLICATIONS I alSIlsSS JWO. ADMINISTRATION MITOMATION DEVEL(PlfMT l SYSTEMS MANAE R MANAGER MANAGERS I B710 B721 B7XI B741 - a
. .Abinistration of . Administration of Dets .Lesign, Development . Provide CPUIS Interface Project Plane & Bene Technology Within & leptementation of . Technical / Scientific &
Schedules (FUN Autoested Office Systems Businese Systems
. Provide (h-Coing . Coordination of Selection, .Adeinletration of -Control of Projects User Sipport Duelgn, laplementation & Company's Computerized -Control of Progrees
. Provide (h-Going Development of Computer Equipeent & r - mi- -Dowelopment of Systees l
User Education System Software & Techniques cations Network -Sipport of Applicatione ,
. Education of Staff . Provide Specialized
)
.Maintonence of User Services to Achieve (5tieum j Profiles & Security level of Technical Effective-
- Access to Computer nees i facilities I
l l l 1/86 . CGIF Pg.12 : 8
ie.&)u/n t
.. I l ,
GPUN/NRCMEETING TMI-l EQUIPENT QUALIFICATION APRIL 18,1986 i I. INTRODUCTION / AGENDA R.F. WILSON II. EQSTATUSELECTRICALCABLES J.F.MANCINELLI A. PAT FINDING B IDENTIFIGTION Of EQ G8LE
- 1. BASELINE
- 2. REVERIFICATION (SINCE PAT FINDING)
C. WHAT HAS BEEN DETERMINED III. EQ CATEGORIES J.F.MANCINELL: A. SPECIFIC ITEMS B. GENERIC ITEMS IV. RESPONSETONRCAPRIL15, LETTER A. HOW MASTER LIST WAS ESTABLISHED L.C.LANESE B. GENERIC ITEMS J. F. ?).N Z LL i ETHODS USED FOR QUALIFICATION ' (0RIGINALANDREVERIFICATION) , C. RESULTS OF REVERIFICATION PROCESS J. F. :').NC:Z: 41f _.
/ . .
~
z i l II. EQ STATUS - ELECTRIGL GBLES PATFINDING REVIEW Of EfV-2 Al8 REVEALED GBLE NOT ON THE THI-l E( NASTER LIST. GBLE WAS IDENTIFIED AS XERITE FR. GPUN READILY DETERMINED GBLE WAS ACCEPTABLE BE GPUNWA0ANOYSTERCREEKFILE,THATENVELOPE0THI-1 ENVIRONMENT. QUALIFIGTION FILE FOR KERITE FR IS COMPLETE. 1
3 IDENTIFIGTION Of EQ GBLE TWO PHASE BASELINE GBLE IDENTIFIGIION PHASEI-REVIEWORIGINALPUNTPR00JREMENTRECORDS POWER & CONTROL GBLE - IDENTIFIED KERITE, WI INSUBTION MISSEDXERITEFRINSUUTION INSTRUMENT GBLE - IDENTIFIE0 CONTINENTAL (ANACONDA), SILICONERUBBERINSUBTION PWASE II - UTILIlE PROCUREMENT & INSTAL B TION E 0R05 FOR RESTART M00lflGTIONS WITH PROCEDURAL CONTROLS FOR FUTURE N00lflGTIONS, TO IDENTIFY THE BAUNCE Of GBLES.
4 i RESULTSOfBASELINEPROGRAMf0RCABLES THEF0LLOWINGCABLETYPESWEREIDENTIFIEDANDQUALIFIED XERITE-WT CONTINENTAL-SILICONERUBBER,FR,FEP BIW-EPRlCSPE SAME M0 ORE - EP0M ROCX8ESTOS-XLPE ( 6
--- -. , , ___- .--- n - , -.. ___-_ _ _ _ , _ _ _ _ . , , , , _ . , _ _ . _ _ , _ . _ _ , _ , , _ _ _ _ . _ . _ _ _ _ _ . . _ _ - - . - . _ _ _ . _ , _ . . _ - - . _ _ _ _ _ _ , _
.. . l G
REVERIFIGTION EFFORT FOR GBLES... F0LLOWING PAT FINDING, REVERIFIGIION Eff0RT WAS PERf0RNED USING PROGREMENT & INSTALLAIION RECORDS PWASEI
~
SCOPEOfEfFORT 171 SPECIFIC COMP 0NENTS
' a 700 CIRGITS RESULT THE KERITE FR GBLE (PAT FINDING) WAS THE ONLY TYP NOTPREVIOUSLYIDENTIFIE0OURINGPWASEI PHASEII SCOPEOf EFFORT 114 SPECIFIC CCMP0NENTS
-450 CIRGITS RESULT ALL GBLE WAS PROPERLY IDENTIFIED OURING PWASE ONE GBLE (BIW SILICONE RUBBER) WAS NOT A00RES IWE QUALIFIGTION PEESS AND WAS SIEE BEEN T0 BE EEPTABLE - REACTOR Bull 0 LNG WIGW LEVEL TRANSHIii!RS(R.G.1.97) l
. g D
6 FIELD VERIFIGTION Eff0RT FOR GBLE SCOPEOf EFFORT EIGHTEQSPECIFICCOMP0NENTS
-TENCIRCUITS RESULTS GBLES WERE UNIDENTIFIABLE FROM PHYSIGL INSPECTION EXPOSED LEETHS VARIED FROM 1 T0 6 FEET IN LEETH i.
BLACKRUBBERTYPEJACKET,NOIDENTIFYIEMARKING COLOR C00E0 SINGLE CON 00CTORS, NO ICENTIFYING i3RKINGS ( e
7 CONCLUSIONS FOR GBLE IDENTIFIGTION REVERIFIGTION EFFORT REINFORCED THE ORIGIML
'hETH000l0GY PWASEI UNIDENTIFIED GBLE RESULTED fB ISOLATED ERROR NOTPROGRMATIC PHASEII
~
G8LE WA0 8EEN PROPERLY IDENTIFIE0 QUALIFIGTION FILE BEING FIMLIlED FOR SIW SIL 1 l _ . _ - - . - _ . . , _ _ _ _ , _ . . ~ _ . . _ , _ , _ , , _ . . . _ , , . , , - _ _ . . . . . _ _ _ _ _ _ , . _ _ , _ _ _ _ , , _ - . . _ _ _ , . . . _ _ . _ _ _ , . . . . , _ , _
8 III EQ CATEGORIES A. SPECIJICITEMS EQ MASTER LIST IDENTIFIES THE VAST HAJ0RIT( O CCMP0NENTS BY UNIQUE TAG NUMBER (285 SPEC
- 8. GENERIC OR CO M N ITEMS ELECTRICALCABLE (7 TYPES)
TERMINALBLOCKS (3 TYPES) SPLICES (4TVPES) EQUIPMENTSEALS (2iYPES) 4
+
[. : 9 THI-l E( MSIER LIST IDENTIFICATION
- 1. OEFINED FIVE (5) BASIC SAFETY FUNCTIONS
- 2. DEFINED DESIGN BASIS ACCIDENTS - ESTABLISHING E@
- 3. OEFINED ASSUNPTIONS
- 4. DEFINED EQ ENVELOPE FOR ACCIDENTS
- 5. DEVELOPMENT Of EQ ESTER LIST A. SYSTEMS RE@ IRED FOR MITIGATION ,
B. IDENTIFIED R.G. 1.97 INSTRUMENTATION C. INTERACTION ITEMS
+
~
10 IDENTIFICATIONOfEQTEMIMLBLOCKS BASELINE FROM REVIEW 0F INITIAL #LX00WN SAMPLING STATES GENERALELECTRIC STANWICX RAYCHEMSPLICESREPLACEDTERMIBLBLOCKSINREACTORBUILDING RE1HRIFIGTION SINCE PAT FINDIE REACTOR BUILDIM (LOG) ALL 8 TEMIML B0XES CONTAINED WCHB SPLICES AS CONFIDED BY E(l EEINEER INTERMEDIATE BUILDING (HELB)
#LX00WN Of ALL SEVEN 0) TEMIML B0XES VERIFIED STATES, GEORRAYCHB AUXILIARY BUILDING (RADIATION 0NLY)
MLX00WNOf130F32TERMIMLB0XESVERIFIEDSTATES,GEAND E CaCtuSICa CONflMED 10BTIFIGTION METW000LCGY IS SOUND ALL I:BTIFIED TEMINAL BLOCKS ARE(L'ALIFIED .
c
~ 11 IDENTIFIGTION 0f SPLICES 8ASELINEMETHOD SAMPLING Of MODIFIGTION 00CUMENTS WALK 00WNSAMPLEINFORMATION 4YCHEM KERITESKV 3M REVERIFIGIION REACTOR BUILDING (LOG) 15 PENETRATIONS-RAYCHEM-QUALIFIED 8TERMINALB0XES-RAYCHEM-QUALIFIED 3 L0 V0LTAGE FAN MOTORS - RAYGEM - QUALIFIE0 VERIFIED BY WALK 00WN OR INSTALLATION 00GMENTATION AUXILIARY BUILDING (RADIATION ONLY) 7 HI V0LIAGE PUMP MOTORS - SKV KERITE - QUALIFIED 6 L0 V0LIAGE PUMP MOTORS - 3M SPLICE - QUALIFIED l VERIFIED BY INSTALLATION 00GMENTATION INTERMEDIATE BUILDING (WELB) 1 TERMINAL B0X - RAYGEM - QUALIFIED j 2 WI V0LIAGE PUMP MOTORS - SKV KERITE - QUALIFIED
! VERIFIEDBYWALK0CWNORINSTALLATIONDCCUMENTATION CONCLUSION l MET:iODOLOGYISSOUND l SPLICESIDENTIFIEDAREQUALIFIED
iz. IDENTIFIGTION Of E@IPMENT SEALS BASELINEREVIEWBYWALX00WNS l REVERIFIGTION CONAkCONNECTORS(SEALS) REACTOR BUILDING (LOCA)
.. 38 COMP 0NENTS RE@ IRING CONNECTORS CONAXCONNECTORS-0VALIFIED VERIFIED BY BASELINE WALX00WN OR 000JMENTATION AUXILIARY BUILDING (RAD ONLY)
N0 EQ COMP 0NENTS RE@ IRE CONNECTORS INTERMEDIATE BUILDING (HELB) . FOUR COMP 0NENTS RE@lRING CONNECTORS CONAXCONNECTORS-QUALIFIED VERIFIED BASELINE WALX00WN CONCLUSION , METH000LOGYISSOUND E@IPMENT SEALS IDENTIFIED ARE @ALIFIED l
V -
, p
_ 13 RESULTSOFREVERIFICATIONEFFORTOfGENERICITEMS METWOOOLOGYFORIDENTIFIGTIONISSOUND AS CONFIRMED BY THE REVERIFICATION Eff0RT PAT FINDING RESULTED FROM AN ISOLATED ERROR GENERIC ITEMS IDENTIFIED ARE QUALIFIED l l l
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