ML20234E052
| ML20234E052 | |
| Person / Time | |
|---|---|
| Site: | 05000000, 05000447 |
| Issue date: | 12/22/1975 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20234A777 | List:
|
| References | |
| FOIA-87-40 NUDOCS 8707070435 | |
| Download: ML20234E052 (4) | |
Text
--_.- _ _-. _ _ __ _ _,
- .},
3 f 1..
.w a
e N
UNITED STATES NUCLEAR REGULATORY' COMMISSION.
DOCKET NO. STN 50-447
. 0, GENERAL. ELECTRIC: COMPANY F
GENER'AL-ELECTRIC STANDARD SAFETY ANALYSIS' REPORT
(, GESSAR-238 NUCLEAR ISLAND STANDARD DESIGN).
NOTICE OF ISSUANCE OF A SAFETY EVALUATION REPORT AND PRELIMINARY DESIGN APPROVA1 Notice is hereby given that the staff of the. Nuclear Regulatory Comission (the NRC Staff) has issued a Safety Evaluation Report (SER) 1 dated; December 1975, and a Preliminary Design Approval No.- PDA-1 dated December 22, 1975,. for the nuclear island portion' of a nuclear power
[lant' as ' described in General Electric Standard Safety Analysis Report (GESSAR-238). -GESSAR-238 was reviewed by the NRC staff pursuantite Appendix 0 to'10 CFR-Part 50.
GESSAR-238 ~contains~ preliminary-safety-related design information.for t
the nuclear island portion of a BWR/6-Mark III boiling Water type nuclear L
power. plant which includes' the nuclear steam supply system (NSSS),
engineered safety feature systems, containment 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 level of 3579 megawatts (1220 megawatts electrical, nominal net).
IU i
8707070435 870610; PDR FOIA THOMAS 87-40 PDR g
W
-)
I s,
,c 4
\\ i l
theSEP.,whichdocumentstheresultsofthestaff'sreviewand i
evaluation of GESSAR-238, including Amendments 1 through 39 thereto, J
l and the design information incorporated by letters from the General Electric I
I Company dated November 21,1975(fromW.GilberttoNRC)andDecember 16, 1975 (from I. Stuart to NRC), integrates and updates the Safety Evaluation Report
]
dated November 1974, and Supplements 1, 2 and 3 thereto, dated December 1974, February 1975, and March 1975, respectively. Moreover, the SER addresses the comments of the Advisory. Committee on Reactor Safebuards (ACRS) as reflected in its report to the Commission dated March 14, 1975.
A copy of the ACRS report is included as Appendix F to the SER.
PDA-1 provides NRC staff approval of the preliminary nuclear island j
design described in GESSAR-238, including Amendment 1 through 39 thereto, and the above described letters from the General Electric Company.
By the 1
issuance of PDA-1, the NRC staff has determined that the design is acceptable for referencing in utility applications for construction permits with the exception of those features of the design for which the staff has identified requirements that differ from those described in the GESSAR-238 document.
These design features relate to tornado missiles, main steam line isolation valve leakage control system interlock, containment purge, and Mark III containment dynamic loading criteria, which are discussed in tSe SER and incorporated as conditions of PDA-1. The GESSAR-238 nuclear 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 licen'se applications for construction permits incorporating by reference the GESSAR-238 nuclear ishnd preliminary l
l
,y
.,,3%.,,
a
re m
1 P".
p
+.. :,..
},,
~."'
4 f
.. l c'
.standerd design unless' there exists significant new information which
!y substantially affects the determinations in PDA-1 or other good cause.
Issuance of PDA-1 and the sfaff's Safety Evaluation Report does L
not constitute.a commitment to issue a permit or license,;or in any way affect.'the authority of the Commission, Atomic Safety and Licensing Appeal:
o i
Board, Atomic Safety and Licensing Boards and other presiding officsrs zin j
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-l 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 impacts associated with any facility proposed to be constructed utilizing the approved reference design will be considered in-
~accordance with the Commission's regulations in 10 CFR Part 51.
PDA-1 is effective as of its date of issuance and shall expire on-December 22,1978,'unless earlier superseded by issuance of an appropriate FDA for the GESSAR-238 nuclear island standard design, or unless extended by the NRC staff.
The' expiration of PDA-1 on December 22,1978, should not affect use of PDA-1 for reference in any construction permit application docketed prior to such date.
i A copy of.(1) the Preliminary Design Approval No. PDA-1 dated December 22. 1975, and Attachment A thereto; (2) the report of the Advisory Committee on Reactor Safeguards dated March 14, 1375; (3) the NRC staff's Safety Evaluation Report, NUREG 75/110, dated December 1975, T
which updates the Safety Evaluation Report dated November 1974, and l
sl ~
-.~...-,,,
_.____.__________________J
, l.. :. ' ^
(
l i
1
.: _u/
. Supplements 1, 2 and '3 thereto, dated December 1974, February 1975, and-March 1975,' respectively;. (4) the" General Electric Standard Safety Analysis Report and Amendments 1 through 39 thereto and letters from the
- t General Electric Company dated November 21, 1975 (from.W. Gilbert to NRC) and' December 16', 1975 (from I. Stuart to NRC); and (5) WASH 1341, the Commission's " Programmatic Information for'the Licensing of Standardized Nuclear Power Plants," dated August 1974, which also includes the Standardization Policy issued on March 5,1973, are available for public inspection at.the Commission's Public Document Room at 1717 H Street, N.W.,
Washington, D.
C.~ 20555.
A copy of PDA-1 and Attachnent A thereto, may be
- obtained upon request. The request should be addressed to the U. S.
Nuclear Regulatory Commission, Washington, D. C. 20555, Attention:
' Director, Division of. Reactor Licensing.
Copies of the Safety Evaluation Report (Document No. NUREG-75/liO) may be purchased at current rates from the National Technical Information Service, pringfield, Virginia 22161.
Dated at Bethesda, Maryland, this.2[ day of December 1975.
FOR THE NUCLEAR REGULATORY COMMISSION STAFF Orig!nn! SignedIg.
John F. Stols i
John F. Stolz, Chief Light Water Reactors Projact Branch No. 2-1 Division of Reactor Licensing
!~
4 l
_ _.. _ _. ~ _