ML20235N504
| ML20235N504 | |
| Person / Time | |
|---|---|
| Site: | 05000447 |
| Issue date: | 12/29/1975 |
| From: | Rusche B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20235M427 | List:
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| References | |
| FOIA-87-40, TASK-IR, TASK-SE SECY-75-746, NUDOCS 8707200105 | |
| Download: ML20235N504 (13) | |
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NUCLEAR RE2ULATl:RY COMMIS$10N INFORMATIO.N REPORT December 79, 1975 srcy.7 fc716
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The Commissioners R.,
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Ben C. Rusche, Director, Nuclear Reactor Regulat;.: p
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Executive Director for Operation's R
Subject:
ISSUANCE OF PRELIMINARY DESIGN APPROVAL - CEE9AR-238 NUCLEAR
_ ISLAND STANDARD DESIGN - DOCKET NO. STN 50-447 g]
Purpose:
To inform the Commission of a completed staff action.
Discussion: Preliminary Design Approval (PD ) No. PDA-1 was issued by the Nuclear Regulatory Com=ission's (NRC) staff on December 22,
1975, to the General Electric Company.- PDA-1 provides staff approval, valid for a period of three years from date of issuance, of the nuclear island design described in the General Electric Standard Safety Analysis Report (GESSAR-238).
Although some of the vendors suggested longer PDA validity periods, the staff believes that the three-year period will permit stabilization of the standardization program while providing flexibility to accommodate changes that may be needed in the reference design.
If a longer PDA validity period is found necessary, the PDA ca.n.be amended accordingly.
GESSAR-238, which was filed in response to option 1 (Reference System) of the Commission's Standardization Policy for nuclear power plants and reviewed pursuant to Appendix 0 to 10 CFR Part 50 contains safety-related design information for the nuclear island portion of a BVet/6-Mark III boiling water type
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nuclear power plant which includes the nuclear steam supply system (NSSS), engineered safety feature systems, containment j
structure, auxiliary building, control building, radwaste building, fuel handling building, and related systems and structures. The GESSAR-238 reference system is designed to operate at a core' thermal power Jevel of 3579 megawatts (1220 megawatts electrical nominal net).
By the issuance of PDA-1, the staff has determined that the deaign is acceptable for referencing in utility applications for construction permits with the exception of those features
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- of.the~ design for which the staff has identified requirements-that differ from'those described in GESSAR-238, relating to tornado missiles, asin steam line isolation valve leakage 1
control system interlock,' containment purge, and containment.
i dynamic load criteria.
The GESSAR-238 nuclear island document, subject to the l
conditions.of PDA-1, will be utilized by and relied upon-by the NRC staff and the ACRS in their' review of facility L
-license applictrions for construction permits incorporating
,j by reference the CESSAR-238 nuclear island preliminary standard design unless there exists significant'new information which l
substantially affects the determinations contained in PDA-1 or other good cause.
PDA-l' provides the NRC staff's first approval of a preliminary-standard design under the Consission'sLStandardization Policy.
Currently, Tennessee Valley Authority's Hartsville and Phipps Bend Plants are now under review for construction permits that-reference this standard design. The Hartsville' preliminary safety analysis report was, accepted for review on November 21, 1974, while the Phipps Bend application wa's~recently docketed on November 7,1975.
Additional detail. relating to the completed staff action fe contained in the PDA-1 and. Federal Register Notice enclesed hereto.
Coordination:
The completed action has been concurred in by the Office of.
1 the Executive Legal Director and the Office of Public Affairs is issuing a public announcement.
The Joint Comnittee on
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l Atomic Energy is being notif d.
k 6 4 Z/ W denC.Rusche, Director Office of Nuclear Reactor Regulation l
Enclosures:
l 1.
Preliminary Design Approval l
No. PDA-1 w/ Attachment A -
Conditions of PDA-1 2.
Federal Register Notice 3.
Press Release 75-290
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GENEP.AL FLECTRIC COMPA';Y l
DOCKET NO. SlN 50-447 CESSAR-23S NUCLEAR ISLAND STANDARD DESIGil PRE..lii!'!ARY D[Sp! APPROVAL (PDS) i Preliminary Design Approyal No. PDA-1 (1)
The General Electric Company has submitted to the Huclear Regulatory Cou:nission's (tmC) Staff for its review a proposed standardized preliminary design for major portions of a nuclcar po.::r reactor of the type dcscribsd in 10 CFR b0.22.
The preliminary design is described in the Ceneral Electric Sten @ed. Se f tty Analysis Report, GESSAR-238 including Icendments 1 throtsh 39 thereto, cnd the design information incorporated by letters from the Cer. oral Electric Ccapany dated Hovster 21. 1975.
(from u. Gilbert to i;aC), and Dec.~aber 16,1975 (from 1. Stuart to IIRC), (h'ercinaf ter collectively referred to as GESSI.n-238).
(2)
CLSSAR-238 contains prelimir.ary design information in accordance with 10 CrH Part 50 Appendix 0, paragreph 3, for the nuclear island portion of a IDlR-6/ Mark 111 toiling water reactor nuclear power plant, which entoa. passes the nuclear steam supply system (iiSSS), engineered safety feature systems, containment structure, auxiliary building, control building, radwaste building, fuel I
handling building, and related systems and structores.
The GESSAR-238 reference design is designed to operate at a core thermal power level of 3579 megawatts (1220 megawatts electrical, nominal net).
(3)
The GESSAR-238 reference design has been reviewed by the NRC Staff and by the Advisory Co:miittee on Reactor Saf,eguards (ACRS).
The results of NRC Staff evaluation of the GESSAR-238 reference design are presented in the Safety Evaluation Report (SER),
NUREG-75/110, dated Decenber 1975, which integrates and updates the information contained in the eari:er Safety Evaluation Report dated November 1974 and three Supplements thereto dated December l
1974, February 1975, and March 1975.
The ACRS comments, including identification of items which the ACRS will review on a case-by-case basis, are set forth in its letter of March 14,1975 (Appendix F of the SLR).
(4)
Based on its review, and the findings set forth in Section 19 of the SFR, the NRC Staff has concluded that subject to the ccnditions set fori.h herein, the information provided in GESSAR-238 with
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l respect to the major portions of the preliminary desian enconoassed i
by GESSAR 233, as described in parMreph 2 above, complies with the l
requirements of 10 CFP. Part 50, Appendix n and is acceptable for incorporation by reference in applications for construction permits.
In accordarce with 10 CFR Part 50, Appendix 0, subject to the condi-
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tions set forth herein and in Appendix 0, the anproved desicn shall be utilized and relied upon by the Staff and the ACP.S in their reviw of any individual facility license application vhich incorporates by reference the approved design, unless there exists significant new
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information which substantially affects the determination set forth in this Preliminary Design Approval or other good cause.
(5)
CESSAR-238 and the GESS/R-233 reference design are accepteble for use es a reference design for construction permit applications:
(a) for f acilities to be located et sitos vihese characteristics conform to the envolt,;.a of site pwameters no,tolated for the z
preli:ainary (Y. inn of thn CNAR-M, reference dedian, which are j
i set fcrth in c!$5/2-22..; provided that (b) tJ,o design of portions of the helcnw nf plPnt whir h interfoce with the accroved de. sign, shall confom to the saiety related interface requiren::nts set forth in GfSSAR-233.
(G)
(a) GE5SAR-238 and the CFSSI.R-238 reference desion are ecceptabic f o r vi,e c.i, a referer.cc design for construction pernit applications, on the condition that the fnur de,ic;n features specified in /ttach-ment A hereto are no iified to conform to the I!RC Staff desion j
requirements described in the !!RC Staff SER in the section specified in Attachment I:..
(b) To the extent that the Gerieral Electric Company subsequently modifies the GESSAR-233 reference design and modifies GESSAR-238 to confern to the Staff requirements, this condition shall be modified accordingly.
11 all four design features are modified to i
conform to the Staff requirements, this condition will be deleted.
(a) This Preliminary Desir n Approval is subject to the satisfactory
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(7) and timely-conpletion of the development and verification test pro-grams described in Table 1-2 of the Safety Evaluation Report and is 1
subject to the satisfactory and timely submission of further information I
concerning the items listed in Table 1-3, " Post-PDA Items", of the SER.
(b) The status of such further information shall be addressed in applications for construction permits referencing CESSAR-238 and will be considered in the Staff review of such applications, i
(8)
This Preliminary Design Approval and all applications for construction permits incorporating it by reference, are subject to all applicable provisions of the Atomic Energy Act, as amended, and the rules and regulations and Orders of the Commission now or hereafter in effect.
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(9). This Preliminary Design Approval does not constitute a commitment-to issue a permit or license or in any way affect the authority of, the Ccm.iission, Ato:aic Safety 'and Licensing Appeal Board, Atomic Safety and Licensing Boards and other presiding. officers.in any proceeding under Subpart G of 10 CFR Part 2.
(10) This Preli-inary Design Approval is effective as of its date of issuance and shall expir'e o'n-December 22, 1978, unless earlier-superseded by the issuance of a Final Cesign Approval for the GESSAR-238 reference design, or unless extended by the i:RC staff.
The expiretion of thi:; PDA on Decader 22, 1970, shall not affect.
the use of this PDA for reference in any construction penait application docketed prior to such date.
FOR THE MUCLEIR REGULATORY C0:*f-lISSIO:i ST/JF f
'7 Roger S.'Coyd,. Acting Director Division of Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Attachment A - Conditions of PDA-1 Date of Issuance:
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GEilERAL ELECTRIC CC:'.?AtlY GEtlERAL ELECTRIC ST/J:DAPD SAFETY A!'ALYSIS REPORT (GESSAR-233 !!UCLEAR ISLA'lD STA';0ARD DESIGil)
!!0TICE OF ISSUA :CE OF A SAFETY EVA' UATIO.'1 PEPD,RT A;D PRELI"I:P.RY J;ESIGri APPRO'.'AL i
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l tiotice is hereby given that the ste.ff of the flutlear Regulatory l
Comiu.ien' (the I RC stuf i) has issuert a Saicty Er.ilo.dioit Repwi ('.' R) dated Decccher 19/5, and a Pralininary Desitj Approval lio. P141 deter!
Decem'x-r 27, 1975, for the nuclear island portien of a nuclear p:reter plant as described.in General Electric Sicndard Sefety Analysis l'.cpart (GESSAR-238).
GESSAR-238 was reviewed by the I:RC staff pursuent it impendix 0 to 10 CTP, Part 50.
GESSAR-238 contains preliminary safety-related design information for the nuclear island portion of a DWR/6-ilark III boiling water type nuclear power plant which include'[ the nuclear steau supply :.ys tem (fiSSS),
engineered ',afety feature syste::.s, containment structure, auxiliary building, control building, radwaste building, fuel handling building, i
and related systems and structures. The GESSAR-238 reference system is designed to operate at a core thermal power level of 3S79 megawatts (1220megawattselectrical,nominalnet).
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1 The SL'R, which documents the results of the staff's review and evaluation of GESSAR-238, including Am.:ndments 1 through 39 thereto, l
1 and the design infor.ation incorporated by letters froa the General' Electric I
Company dated November 21,1975 (from W. Gilbert to URC) and December 16, 1975 (trom 1. Swart to Ul;C), integrat'es' and updates trm Wfety Evaluation Hepot t dated Covea.ber 1974, and Supplements 1, 2 and 3 tnereto, d6ted Datenber 1974, February 1975, and Mcrch 1975, respectively. Marcover, the SEH addrcsses the comments of the Advisory Conn.ittee on Reactor Safebuards (ACRS) cs reflected in its report to the Cou.ission dated iP.rch 14, 1976.
A copy of the ACRS j
report is included a', f.ppendix F to the SER.
PDA-1 provides MRC stcff approval of the preliuira:ry nucicar island design describcd in C' bbAR-230, including Aacudent 1 Liira.,gh 39 thereto, J
and t'he above descriled letters f rom t he General OccLric Company.
By the issuance of PDA-1, the URC stoff has determined thct the design is acceptable for referencing in utility applications for construction permits with the exception of those features of the desjgn for which the staff has identified 4
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requirements that differ from those described in tne CESSAR-238 document.
These design features relate to tornado missiles, main steam line isolation valve leakage control system interlock, containment purge, and Mark III containment dynarnic loading criteria, which are discussed in the SER and incorporated as conditions of PDA-1. The CESSAR-?38 nucicar island design as described in that document subject to the conditions of the PDA-1, shall be utilized by and relied upon by the NRC staff and the ACRS in their review of facility license applications for construction permits ir.corporating by refererite the GESSAR-238 nucicar island preliminary
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standard design unless there exists sige.ificant new information which
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substantially affects the determinations in PDA-1 or other good cause.
Issuance of PDA-1 and the staff's Safety Evaluation Report does not constitute a co 7.itt.ent to issue a permit or license, or in any way affect the authority of the Commission,. Atomic Safety and Licensing Appeal Board, Atomic Safety and Licensing Boards and other presiding officers in 1
any proceeding under Subpart G of 10 CFR Part 2.
This action only approves the design of a facility for use for reference purposes in applications for permits to construct a nuclear power plant.
It does not authorize the construction'or operation of any nuclear power plant or any other facility.
The environmental iu;ncts associated with any facility proposed to be constructed utili/.ing' the approved reference design will be considered in acc,ordance with the Co. nission's regulations in 10 CFR Part 51.
PDA-1 is effective as of its date of issuance and shall expire on' 1
l December 22, 1978, unless 'carlier superseded by issuance of an appropriate FIA l
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for the GESSAR-23B nuclear island slant'ard design, or unless extended I
by the !;RC staff.
The expiration of PDA-1 on Decer.iber 22,1978, should not affect use of PDA-1 for reference in any construction permit application l
l docketed prior to such date.
A copy of (1) the Preliminary Design Approval lio. PDA-1 dated l
December 22, 19,75, andAttachmentAthereto;(2)thereportofthe Advisory Committee on P.eactor Safeguards dated l' arch 14,, 1975; (3) the NRC staff's Safety Evaluation Report, t,"JREG 75/110, dated December 1975, which updates the Safety Evaluation Report dated iovember 1974, and
. Supplements 1, 2 and 3 thereto, dated December 1974, February 1975, and March 1975, respectively; (4) the General Electric Standard Safety Analysis Report and kendrents 1 tnrough 39 thereto and letters from the General Electric Company dated Ho5cEber 21,1975 (from W. Gilbert to 11RC) and December 16, 1975 (from I. Stuart to NRC); and (5) UASH 1341, the Conmission's "Progroun: tic Infonaation for the Licensing of Standardized fluclear Power Plants," dated August 1974, which also includes the 1
1 Standardi/ation Policy issued on March 5, 1973, are availabic for public i
inspection at the Co:.;::ission's Public Document Room at 1717 il Street, N.W.,
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Washington, D. C. 20555.
A copy of PDA-1 and Attachment A thereto, may be obtained upon request.
The request should be addressed to the U. S.
fluci, ear Regulatory Commission, Washington, D. C. 20555, Attention:
Director, Division of Reactor Licensing.
Copies of the Safety Evaluation Report (Document ilo. NUREG'-75/110) may be purchased at current rates from the fiational Technicel Information Service, Springficid, Virginia 22161.
Dated at Bethesda, l'aryland, this 2).n.L day of December 1975.
FOR THE NUCLEAR REGULATORY C0:'3ISSION STAFF l
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F. Stolz, Chief l
Li t Water Reactors oject Branch No. 2-1 Division of Reactor Licensing I
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i UNITED STATES l
NUCLEAR REGULATORY COMMISSION J
WASHINGTON, D. C. 20555 1
No.
7S-2tl0 l'OR IMMHlil ATl; Hiil,hAS1!
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Contact:
Clare Miles (Mailed - December 22, 1975)
Tel.
301/492-7771 NRC STAFF ISSUES FIRST PRELIMINARY DESIGN i
APPROVAL OF STANDARDIZED NUCLEAR POWER PLANT In a step toward standardization, the Nuclear Regulatory J
Commission staff today issued the first Preliminary Design Approval for a standard nuclear power plant.
PDA-1 was issued to the General Electric Company.
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Benard C. Rusche, Director of the NRC's Office of Nuclear I
l Reactor Regulation, said in announcing the action:
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" Advancing the concept of standardization is a major goal of the Commissioners, in that it would further enhance the margin of safety and offer advantages in scheduling, construc-l tion and operation.
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"In addition to the General Electric PDA, we have almost l
completed work on two other applications for standardized l
design--from Combustion Engineering and Westinghouse.
We l
expect to issue Preliminary Design Approvals on these shortly, l
l Several other applications still are under review."
l The PDA issued today is for the preliminary standard nuclear island design portion of a 1220 megawatt (electric) plant as described in the General Electric Standard Safety Analysis Report (GESSAR-238).
GESSAR-238 contains safety-related design information for the nuclear island portion of a BWR/6-Mark III boiling water type nuclear power plant which includes the nuclear steam supply system, engineered safety features, containment structure, auxiliary building, control building, radwaste building, fuel handling-building, and related systems and structures.
l Issuance of the PDA follows completion of the NRC staff Safety Evaluation Report (SER) which included the advice of the Advisory Committee on Reactor Safeguards.
By issuing PDA-1, the staff has determined that the design is acceptable for referencing in utility applications for nuclear power plant A
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2-75-290 licenses except for some items which are discussed in the SER and incorporated as conditions of the PDA-1.
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The GESSAR-238 nuclear island document, subject to the conditions of PDA-1, will be used by the NRC staff and the ACRS in their review of applications for construction permits incorporating by reference the GESSAR-238 nuclear island pre-liminary standard design unless significant new information is developed which substantially affects the determinations con-tained in PDA-1 or for other good cause.
Mr. Rusche said that PDA-1 can be referenced in construc-l tion permit applications docketed over the next three years.
"Since up to 18 menths may be required for processing a con-struction permit, that means the PDA will have an effect on plants on which construction is started over the next four and one-half years," he said.
I PDA-1 does not constitute a commitment for permits or licenses for a utility referencing the design.
Applications for specific plants would be subject to the NRC hearing process.
i A Final Design Approval (FDA) will be issued when final i
design information has been reviewed and found acceptable to the NRC staff and the ACRS.
Currently, applications for Tennessee Valley Authority's Hartsville and Phipps Bend plants, now under review for con-struction permits, reference this standard design.
The Hartsville preliminary safety analysis report--part of the construction permit application--was accepted for review on November 21, 1974, and the Phipps Bend application was recently docketed on November 7, 1975.
. A copy of the Preliminary Design Approval and the Safety l
Evaluation Report will be available for inspection at the NRC l
Public Decument Room, 1717 H Street, N.W., Washington, D.C.
Single copies of the PDA may be obtained by writing to the l
Nuclear Regulatory Commission, Washington, D.C. 20555, attention:
Director, Division of Reactor Licensing.
The Safety Evaluation l
Report (NUREG-75/110) may be purchased at the National Technical Information Service, Springfield, Virginia 22161 for 59.25.
1 2
I DISTRIBUTION NO. OF COPIES Secretary 5
Chairman Anders 4
-Commissioner Rowden 2
Commissioner Mason 3
Commissioner Gilinsky 2
I Commissioner Kennedy 3
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Exec Dir for Operations, 2
Asst Exec Dir for Operations 1
Congressional Affairs-2 Public Affairs 2
General Counsel 5
Inspector & Auditor 2
Exec Legal Director 2
Adminstration 3
i Polic; Evaluation 2-Planning &' Analysis 1
Mgmt Information & Program Control 1
Special Studies 1
Nuclear Reactor Regulation 2
Reactor Licensing 3
Technical Review 1
Standards Development 4
j Nuc Mat Safety & Safeguards 2
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Inspection & Enforcement 3
Nuclear Regulatory.Research 2
ACRS 1
AS&LBP 2
AS& LAP 2
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