ML20054F211
| ML20054F211 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 06/02/1982 |
| From: | Davidson D CLEVELAND ELECTRIC ILLUMINATING CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8206150317 | |
| Download: ML20054F211 (38) | |
Text
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!ill t N D ELECT RIC ILLUMIN ATIN C CD:
!: ' Y ILLUMINATING BLOG. e PUBUC $00Amt a cLIVELAND. OHlo 44101 e TELEPHONE (216) 6231350 e MAIL ADDRESS:
P. O. BOX 5000 Semn] The Best Locat.on in :he Nation Dafwyn R. Davidson viCE PRISiOENT Sv5f f u ( NGtNE E RING AND CONSTRUCilON June 2, 1092 Mr. A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Mr. Schwencer:
Perry Nuclear Power Plant Docket Nos. 50-440; 50-441 Equipment Qualification Meeting on May 12, 1982, members of my staff and several consultants met with the Equipment Qualification Branch of NRR and personnel from Region IV and Headquarters of I&E. The purpose of the meeting was to discuss several areas concerning Perry's Equipment Qualification Program.
The purpose of this letter is to document the substance of that meeting as we perceived it.
We would appreciate your concurrence or comments on these minutes. This will help insure that our EQ program is consister.t with NRC requirements.
Very truly yours, 0 b $4+1 h Dalwy
. Davidson Vice President System Engineering and Construction DRD: dip cc: Jay Silberg, Esq.
John Stefano Max Gildner
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0206150317 920602 PDR ADDCK 05000440 A
I PERRY NUCLEAR POWER PLANT EQUIPMENT QUALIFICATION MEETING WITH NRC/EQB ON MAY 12, 1982 The following is our understanding of the staff's response, comments and concerns for each of the major meeting agenda items:
Cround Rules 1.
The Perry FSAR review will be conducted by the NRC on the basis of Revision 2 of the Standard Review Plan (NUREG-0800).
2.
The Perry FSAR is not presently structured around the format required by NUREG-0800. The NRC does not require it to be completely restructured, only ensure that it addresses the issues contained in the SRP.
3.
The NRC will expect that prior to a site audit, at Icast 85% to 95% of the generic types vf equipment are qualified and installed. A minimum of one of eact type of device must be installed. Any items which are undergoing long term testing at the time of the site audit will be considered by the staff as being in the 85%-95% group.
i 4
For plants which start-up after June 30, 1982, the staff will consider fuel load as the first outage for the purpose of complying with the "two refueling outages from June 30, 1982, and no later than November 30, 1985, within which to be completely qualified". Requirements of 10CFR50.49.
5.
In order to minimize the impact at the 0.L. hearing of open issues in their SER, the NRC agreed to provide the results of this review of the Perry Environmental Qualification Program in the SER.
6.
The staff requested that the FSAR include a discussion of the safety functions of those devices / systems noted in Table 3.2-1 of the FSAR.
The staff reiterated that they do not want an equipment list in the FSAR.
Equipment "Important to Safety" 1.
Assurance needs to be made that the failure of a non-lE device would not fail a IE device.
2.
The NRC's Human Factors Branch will review the Perry Emergency Operating Procedures to assure that there are no devices in the procedure which would mislead the operator.
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Mild Environment Equipment 1.
The Product Quality Certification (PQC) is acceptable to the NRC.
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Equipment Qualification Meeting Page 2 Procurement of Safety Related Spare Farts and Components 1.
The staff will require the environment in which the spare and replacement parts are stored be controlled so as not to affect their qualification.
2.
The staf f has taken the position that replacement with parts of the "same kind" is acceptable. There is no need to qualify individual items.
3.
There should be some sort of analysis to assure that over a period of time, the use of replacement components will not change the electrical performance or characteristics of a device.
Environmental Qualification of Mechanical Equipment 1.
The Perry position on the attached transparencies should be put into the FSAR section 3.11.
2.
Provide assurance that CDC4 is met.
3.
The Perry position, as presented, should be acceptable if Perry includes a listing of equipment and expands on the justification.
4.
Perry needs to take a look at the radiation effects on lubricants and present the position in the FSAR.
Independent Verification of Reactor Safety 1.
This is a mandatory program, now called by the NRC, the " Equipment Qualificatlon Test Inspection Program".
It is predicated on 10CFR50.49, and 10CFR50 Appendix A GDC 11.
2.
This program will be run by the NRC's Region IV Office of Inspection and Enforcement. The program will be basically a QA program (i.e., confirm testing was done to the manner described in the associated test plan). Questions dealing with the technical content of a test will be forwarded to the NRC/EQB by Region IV for resolution.
3.
The results of the Region IV inspection will be provided as input to SER's, 4.
Region IV will have no review function but will make constructive comments on the test plans.
5.
Region IV will work through the applicant / licensee rather than directly with I
vendor / test lab to arrange for what tests they wish to observe and what test plans they wish to review. All inspections will be pre-announced.
6 The question on "Who resolves conflicts between Region IV and the utility?"
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was discussed, however, Perry is confused on how this will be handled.
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3 Equipment Qualification Meeting Page 3 Justification for Interim Operation 1.
The justification must address the 10CFR50.49 requirements.
2.
The Justification for Interim Operation should not be submitted until about two months prior to fuel load.
The staff will review at any time the submittal which delineates how such a justification would be based.
CE Phase III Program Status 1.
The staff wants one of the examples that will be submitted with the GE Licensing Topical Report to be representative of a device subject to hydrodynamie. Ioad qualification.
KAM/iw 5/21/82 l
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PERRY NUCLEAR POWER PLANT EQUIPMENT QUALIFICATION MEETING WITH NRC/EQB ON MAY 12, 1982 Meeting Attendees Nawa Organization John J. Stefano NRR/DL Marcel R. Harper NRR/DE/EQB Jim Kennedy NRR/DE/EQB J. R. Agee NRC/RIV Paul Shemanski NRC/NRR/DE/CQB Goutam Bagchi NRC/NRR/DE/tyB W. V. Johnston NRC/NRR/DE Siavosh Dehdashti GE/ SED Doug Pike Niagara Mohawk 9 Mile 2 Neil DellaGreca Stone & Webster - 9 Mile 2 Arie Bluh Stone & Webster - River Bend Alan Chan Stone & Webster - River Bend Joe Weiss Quadrex Noel Shirley GE/SW Nancy Chapman Bechtel Power Tony Cappucci ACRS/NRC Peter Thompson Public Service Electric & Gas Steve Danielson NuTech Engineers Matee Rahman Gulf States Utilities (River Bend)
Ron Oprea Gulf States Utilities (River Bend)
R. W. Kemp General Electric David Sharp Gulf States Utilities (River Bend) l Zoltan R. Rosetoccy NRC/NRR/EQB L. D. Test GE G. W. Reinmuth NRC-IE A. E. Dohna Torrey Pines Technology Arthur Butt Torrey Pines Technology Tom Flemming Gilbert Associates Frederick Larouski Gilbert Associates l
N. B. Le NRCC/IE Todd Allen Bechtel Power / Hope Creek David D. Reiff NRC/NRR/EQB Bob LaGrange NRC/NRR/EQB Gus Kephodes Richner Power Corp.
Forrest E. Hatch General Electric Company Kenneth A. Matheny Cleveland Electric Illuminating Co.
Bill Coleman Cleveland Electric Illuminating Co.
Larry Rougeux Cleveland Electric Illuminating Co.
David Green Cleveland Electric Illuminating Co.
Larry E. Wise Gilbert Associates H. Shannon Phillips NRC RII Vendor Pgm Fr, EQ Section l
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'g PERRY NUCLEAR POWER PLANT UNITS 1 AND 2 I
EQUIPMENT QUALIFICATION PROGR A M l
l THE CLEVELAND ELECTRIC ILLUMINATING COMPANY 1
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PERRY NUCLEAR POWER PLANT EQilIPMENT QUALIFICATION MEETING WITH NRC/EQB MAY 12, 1982 l
e INTRODUCTION BILL COLEMAN e
GROUND RULES BILL COLEMAN e
EQUIPMENT "IMPORTANT TO KEN MATHENY SAFETY" e
MILD ENVIRONMENT EQUIPMENT KEN MATHENY I
e PROCUREMENT OF SAFETY RELATED MIKE LAZAR SPARE PARTS AND COMPONENTS e
ENVIRONMENTAL QUALIFICATION KEN MATHENY OF MECHANICAL EQUIPMENT e
INDEPENDENT VERIFICATION OF DISCUSSION REACTOR SAFETY (IVRS) e JUSTIFICATION FOR INTERIM JOE WEISS OPERATION e
GE PHASE III PROGRAM STATUS FOREST HATCH
PERRY lluCLE'AR POWER PLANT EQUIPMEllT OUALIFICATION MEETII1G WITH NRC/E0B FEBRUARY 23, 1982 INTRODUCTION BILL COLEMAN PNPP EQUIPMENT QUALIFICATION PROGRAM KEN MATHEllY GAli (BOP) PROGRAM LARRY WISE GE (GSSS) PROGRAM FORREST HATCH HARSH / MILD ENVIRONMENT LARRY WISE
. RADIATION SOURCE TERHS JACKIE TATE
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DISCUSS 10!1
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PERRY NUCLEAR POWER PLANT EQUIPMENT OUALIFICATION GROUND RULES I
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WHAT REVISION OF THE " STANDARD REVIEW PLAN" IS THE EQUIPMENT OUALIFICATION BRANCH USING FOR THE REVIEW OF THE PERRY FSAR?
l MAY 12, 1982 i
PERRY NUCLEAR POWER PLANT 4
EQUIPMENT OUALIFICATION GROUND RULES S
WHAT REVISION OF THE " STANDARD FORMAT AND CONTENT OF SAFETY ANALYSIS REPORTS" IS IN SYNC. WITH THE " STANDARD REVIEW PLAN" BEING USED BY THE EQUIPMENT OUALI-FICATION BRANCH FOR THE REVIEW OF THE PERRY FSAR?
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MAY 12, 1982 i
~4 PERRY NUCLEAR POWER PLANT EOUIPMENT DUALIFICATION GROUND RULES 4
1 4
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O WHEN WILL THE EQUIPMENT QUALIFICATION BRANCH REVIEW THE TEXT OF SECTIONS 3.10 AND 3.11 OF THE PERRY FSAR?
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MAY 12, 1982 i
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PERRY NUCLEAR POWER PLANT EQUIPMENT QUALIFICATION GROUND RULES a
WHAT ARE THE SPECIFIC REQUIREMENTS FOR THE NRC SITE AUDIT?
PERRY NUCLEAR POWER PLANT EQUIPMENT QUALIFICATION GROUND RULES PROPOSED ACTION PLAN:
o FSAR SECTIONS 3:10 AND 3:11 REVISE TEXT TO AGREE WITH PERRY NUCLEAR POWER PLANT, EQUIPMENT QUALIFICATION PROGRAM.
DELETE EQUIPMENT LISTS.
REVISE " ENVIRONMENTAL ZONES AND LIMITS" TABLES SUBMIT TO NRC FOR REVIEW ON AUGUST 15, 1982 o
SUBMIT LIST OF SAFETY RELATED EQUIPMENT LOCATED IN A HARSH ENVIRONMENT TO THE NRC FOR REVIEW ON SEPTEMBER 1,1982 e
SUBMIT " JUSTIFICATION FOR INTERIM OPERATION " TO THE NRC FOR REVIEW ON SEPTEMBER 1, 1982.
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NRC SITE AUDIT ON MARCH 1, 1983.
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PERRY NUCLEAR POWER PLANT EQUIPMENT QUALIFICATION EQUIPMENT "IMPORTANT TO SAFETY" e
PERRY EQUIPMENT QUALIFICATION PROGRAM FOR ELECTRICAL EQUIPMENT ADDRESSES CLASS IE EQUIPMENT.
I e
FOR PERRY:
"IMPORTANT TO SAFETY" = CLASS IE e
RATIONALE R.G. 1.97 REV. 2 CAT. I AND II INSTRUMENTATION TREATED AS CLASS IE AND COVERED UNDER E.Q. PROGRAM.
CAT. III INSTRUMENTATION IS NOT REQUIRED TO BE CLASS IE AND IS NOT COVERED UNDER E.Q. PROGRAM.
R.G. 1.75 REV. 2 ONLY ASSOCIATED CIRCUITS ARE TO HEATERS IN M0V'S.
QUALIFIED AS AN INTEGRAL PART OF MOV.
EMERGENCY OPERATING PROCEDURES. MAKE USE OF NON SAFETY RELATED EQUIPMENT, IF AVAILABLE. NO NEED TO QUALIFY THIS NON SAFETY RELATED EQUIPMENT.
IF SOMETHING IS "IMPORTANT TO SAFETY" THEN IT HAS A CLASS IE POWER SUPPLY.
IF IT HAS A CLASS IE POWER SUPPLY IT WILL BE COVERED UNDER E.Q. PROGRAM.
MAY 12, 1982
" PERRY NUCLEAR POWER PLANT EQUIPMENT QUALIFILATION MILD ENVIRONMENT EQUIPMENT e
B0P SPECIFIED FOR IEEE 323-1974 AND 344-1975.
e NSSS SPECIFIED FOR IEEE 323-1971 AND 344-1971.
SEISMIC QUALIFICATION RE-EVALUATION. (INCLUDING HYDRODYNAMICS )
+
PRESENTLY BEING CONDUCTED FOR ELECTRICAL AND MECHANICAL EQUIPMENT.
+
DOCUMENTATION WILL BE IN AUDITABLE FILE AT PERRY SITE.
ENVIRONMENTAL QUALIFICATION
+
DOCUMENTATION FOR IEEE 323-1971 AT NSSS VENDOR.
+
PQC IN AUDITABLE FILE AT PERRY SITE.
e NO FURTHER ENGINEERING ACTION FOR MILD ENVIRONMENT SAFETY RELATED EQUIPMENT.
}i[j PRODUCT-QU ALITY CERTIFICATIONl000RMWS40A092WM48itt8iWgy ra uctwaws v. t,,3.
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CONTROLLED OUALITY ASSURANOE PROCRAM AND ARE IN CONFORMANCE WITH THE PROCUREflENT y
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QUALITY REQUIREMENTS INCLUDING APP L1 CABLE CODES, STANDARDS AND SPECIFICATIONS AS IDENTIFIED IN THE ABOVE-REFERENCED DOCuraENTS, UNLESS NOTED BELOW. ANY SUPPORTINC DOCUMENTATION
'ITHER ATTACHED, OR WILL BE V ORWARDED OR RETAINED IN ACCORDANCE WITH CONTRACTUAL REQe: REMET 4TS.
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PERRY NUCLEAR POWER PLANT EQUIPMENT 00ALIFICATION MILD ENVIRONMENT EQUIPMENT PERRY HAS DEVELOPED AN EQUIPMENT OUALIFI-CATION PROGRAM MANUAL.
APPENDIX "A"
IS THE ENVIRONMENTAL CONDITIONS AND LIMITS AND OUR CLASSIFICATION OF HARSH / MILD ENVIRONMENTS.
WILL THE E0B REVIEW THIS PERRY SPECIFIC DATA FOR VERIFICATION OF OUR CLASSIFICA-TION OF HARSH / MILD ENVIRONMENTS?
_1 SPARE PARTS PROCUREMENT A method fbr the procurtement of, spare parts t; hat will not inva(idate Perry Plant's Equipment Qualification Program.
This program is based upon:
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- 1) Quality Items List PA0304 A procedure to provide a file that details the safety classification and seismic category for plant equipment and their respective component parts.
- 2) Procurement of Services, Spare Parts Material and-Replacement Components PA 0402 Establishment of the requirements for the procurement of items without using or amending.an existing purchase agreement.
- 3) Engineering Evaluation Basis Document (EEB)
The Procurement Document Enginnering Evaluation Basis Form documents that safety-related, seismic-cat; gory, and special QA required items are requisitioned under requirements at least equivalent to that of the original equipment, or those specified by a properly reviewed and approved revision of CAI, CE, or other design agent's procurement specification.
It demonstrates that sufficient design information is available in existing, approved design documents. The basis form information i
also provides the input to maintain the Q-List accurate and current.
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A HULTILEVEL PROCUREMENT POLICY IS PROPOSED TO PROVIDE i
THE PROCEDURE TO COMPLETE AN EEB.
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THE EEB WILL BE THE VEHICLE TO DOCUMENT HOW THE DECISIONS I
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WERE REACHED.
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QUESTIONS REMAIN ON HOW TO FILL OUT AN EEB.
k' hat are the receipt inspection requirements?
The QA Require::ents?
t The Procurement Requirements?
The multilevel procurement procedure would delineate lists of each type.
QA Receipt Inspection Procurement Other 1.
1.
1.
1.
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L The engineer filling out the EEB would then only have to list the ones he wants on the EEB.
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i The question remains, how does the engineer know which ones to include on each EEB?
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Answer: Multilevel procurement, a logic ficru path to enable the engineer a means of selecting the necessary
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requirements.
separate cate;;ories, Jtem each having specific needs.
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PHASE I ITE (1)
(2)
Q-List PAP-0304 (3
Commercial NO Hodified No /Esspntia l Quality QA?
FunEtio
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Yes Yes 5
PIL-\\SE II Nee Yes Item?
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No 6
Determin Yes No Y 0ne if COC Hf ?
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I I Procurement PHASE III Level l
(8)
(9)
MFG.
REQ.
(10) 1 Receipt t
Inspection Req.
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Enter Into D/B i
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DEFINITIONS l
SYSTEM:
A COLLECTION OF COMPONENTS, EQUIPMENT, VALVES, INSTRUMENTS, P!P!NG, CABLING, AND ASSOCIATED STRUCTURES THAT PERFORM A FUNCTION.
I COMPONENT:
A PIECE OF EQUIPMENT, VALVE, INSTRUMENT, PIPING, CABLING OR ASSOCIATED STRUCTURE USED IN A SYSTEM.
SYBASSEMBLY:
A PIECE OF A COMPONENT CONSISTING OF A NUMBER OF PARTS.
I PART:
AN INDIVIDUAL ITEM FROM WHICH EQUIPMENT, VALVES, INSTRUMENTS, AND ASSOCIATED STRUCTURES ARE ASSEMBLED.
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CATEQQRIZE PARTS o
EXTEND Q-LIST TO IDENTIFY ALL SPECIPIC 5AFETY-RELATED EQUIPMENT, VALVES, INSTRUMENTS.
(ELECTRICAL AND MECHANICAL) e DETERMINE SPECIFIC SAFETY FUNCTION (5) FOR EACH EVENT (MODE OF OPERATION) q DETERMINE PARTS THAT ARB REQUIRED TO OPERATE OR THAT CANNOT FAIL IN ORDER, TQ SUPPORT THE SAFETY FUNCTION e
CATEGORIZE PARTS AS NON-SAFETY RELATED OR SAFETY RELATED e
DETERMINE STRUCTURES AND CONSUMABLES NEEDED TO SUPPORT COMPONENT SAFETY FUNCTIONS TORREY PINES TECHNOLOGY A DV400N CF CE6 ATC7v1C Cf74VWY
SOLE SOURCE o
OETERMINE THICH SAFETY-RELATED PARTS ARE REPLACEMENT PARTS /CONSUMABLES e
CATEGORIZE THE REPLACEMENT SAFETY-RELATED PART5/CONSUMABLES INTO TWO GROUP 5s 4)
THOSE THAT MUST BE PROCURED FROM A SOLE SOURCE I
7)
THOSE THAT MAY BE PROCURED FROM MORE THAN ONE SOURCE e
ESTABLISH GENERIC PARTS, WHERE POSSIBLE A OrVTEN CF CX74RAl. AM CIPvS%NY
PROCUREMENT METHOD 4
DETERMINE METHOD OF PROCUREMENT FOR EACH PART/ CONSUMABLE e
METHOD 1.
SPECIFICATION METHOD II.
REPLACEMENT IN KIND METHOD VERIFICAT!QN METHOD IV.
CATALOG MEHTQD i
V.
GQ W ERCIAL METHOD
i SUPPLIER QA SYSTEM REQUIREMENTS e
10CFR30 APPENDIX 5 REQUIREMENTS FOR EACH PROCUREMENT METHOD I.
SPECIFICATION METHOD REQUIRED II.
REPLACEMENT IN KIND METHOD REQUIRED III.
VERIFICATION METHOD NOT REQUIRED IV.
CATALOQ METHOD QA PROGRAM REQUIRED NOT TO 10CFR50 Y,
CoMy.,ERCIAL METHOD NOT REQUIRED e
PARTICIPATE IN NATIONAL INDUSTRY QA SURVEY SYSTEM TORREY PINES TECHNOLOGY A CFAEBON CF CEFEf4AL ATCPAC CX FM MNY
SUPPI,IER DOCUMENT REQUIREMENTS I.
SPECIFICATION METHOD:
IN ACCORDANCE WITH THE SPECIFICATION COULD INCLUDE MATERIAL TEST REPORTS, SPECIAL TEST REPORTS, C OF C, ETC.
II.
REPLACEMENT IN KIND METHOD:
SUPPLIER C OF C (SOLE SOURCE) 8 III.
VERIFICATION METHOD:
NONE IV.
CATALOG METHOD:
SUPPLIER C OF C V.
COMMERCIAL METTIOD:
NONE TORREY PINES TECHNOLOGY A OvitKN CF CEffAAL. ATCMC NN
s ACCEPTANCE REQUIREMENTS I.
SPECIFICATION METHOD:
SOURCE VERIFICATION, RECEIVING INSPECTION OR SUPPLIER C OF C II.
REPLACEMENT IN KIND METHOD:
SOURCE VERIFICATION, RECEIVING INSPECTION. OR SUPPLIER C OF C i '
l III.
VERIFICATION METHOD:
RECEIVING INSPECTION OR INDEPENDENT TESTING LABORATORY IV.
CATALOG METHOD:
RECEIVING INSPECTION OR SUPPLIER C OF C V.
COMMERCIAL METHOD:
RECEIVING INSPECTION TORREY PINES TECHNOLOGY A CIVGON & CEPERAL ATm1C COPW %NY
MAINTAIN DOCUMENTATION t
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COMPUTER DATA BASE I
e COMPONENT DOCUMENTATION FILE AND MAINTENANCE RECORDS e
PART DOCUMENTATION FIL.E j
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SUPPLIES FILE, QA RECORDS I
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TORREY PlNES TECHNOLOGY 4 - c,crmw.r= =,wu
PERRY NUCLEAR POWER PLANT 4
EQUIPMENT OUALIFICATION ENVIRONMENTAL QUALIFICATION OF MECHANICAL EQUIPMENT S WHAT PERRY HAS DONE
-- CONDUCTED STUDY TO DETERMINE SYSTEMS REQUIRED FOR THE SIX SAFETY OBJECTIVES.
-- IDENTIFIED ORGANIC PARTS AND COMPONENTS FOR BOP EQUIPMENT.
(ELECTRICAL AND MECHANICAL) 9 WHAT PERRY WILL DO
-- IDENTIFY ORGANIC PARTS AND COMPONENTS FOR NSSS EQUIPMENT.
(ELECTRICAL AND MECHANICAL)
-- DEVELOP PROCEDURES TO PROCURE PARTS AND COMPONENTS COMMENSURATE WITH THE SPECIFIC SAFETY FUNCTION (S).
-- ESTABLISH A SOUND PREVENTITIVE MAINTENANCE PROGRAM.
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PERRY NUCLEAR POWER PLANT EQUIPMENT QUALIFICATION IVRS o
WHAT IS REGION IV CHARTER ON IVRS?
o IS THERE ANY OVERLAP IN RESPONSIBILITIES OR REVIEW?
o WHAT IS THE BASIS FOR REGION IV REVIEW CRITERIA?
1 o
WHO RESOLVES CONFLICTS BETWEEN REGION IV AND UTILITY?
i
)
PROGR.iM FOR JUSTIFYING INTERIM OPERATION OF THE PLANT DURING ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMEllT C3 QUADREX l
('
07 JAN 82 REV*
PERRY NUCLEAR POWER PLANT PAGE 3c-1 EQUIPMENT OUALIFICATION PROGRAM
~*
7 ROUP ors 4tg CLASS tt.:
COMPONKNg3 1
ROUP AFFECTED I
BY EVENT 4.1 UALIFICATION3 (LOCA)
ORALTERNAT(yp,f g
NEEDED D R EVENT 4.1 (LOCA)
GROUP NEEDED TO
/
PERFORM SIX SAFETY
/
OBJECTIVES FOR i
/
EVENT 4.1 (LOCA)
/
1 J
v-CMOUP OF CLASS lE I
COMPONENTS AFFECTED W ffARSH ENVIRONMENTS D ONE OR MORE EVENTS l
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l FIGURE 1-2:
GRAPlt t'd REPRESENTATION OF THE SEGMENTED TREATMENT OF ACCIDt.Nr;; AND REQUIRED EQUIPMENT TO DETERMINE THE i
BASIS D)R INTERIM OPERATION.
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PERRY NUCLEAR POWER PLANT
"-6 PAGE
,EQUIPM_ENT OUALIFIC'\\IlON PROGRAM
PERRY NUCLEAR POWER PLANT EQUIPMENT DUALIFICATION JUSTIFICATION FOR INTERIM OPERATION THE PERRY STUDY BEING CONDUCTED FOR JUSTIFICATION OF INTERIM OPERATION WILL BE COMPLETED BY JULY 1, 1982.
WILL THE E0B REVIEW THIS REPORT?
HOW SHOULD IT BE SUBMITTED?
WHEN SHOULD IT BE SUBMITTED?
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e PERRY NUCLEAR POWER PLANT EQUIPMENT QUALIFICATION GE PHASE III STATUS e
TOPICAL REPORT MOVING ALONG ON SCHEDULE e
NRC START REVIEW JUNE 1982 e
5 EXAMPLES BEING DEVELOPED USING TOPICAL PROCEDURES I
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