ML031210181
| ML031210181 | |
| Person / Time | |
|---|---|
| Issue date: | 01/29/1981 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| %dam200609 GL-81-008, NUDOCS 8102260268 | |
| Download: ML031210181 (5) | |
Text
-
- - 06 R b so -UNITED STATES
'::I A :NUCLEAR REGULATORY COMMISSION
- WASHINGTON, D. C. 20555-January 29, 1981 ALL
- HOLDERS'OF CONSTRUCTION PERMITS AND OPERATING LICENSES FOR BOILING WATER REACTORS
SUBJECT:
ODYN CODE.(GENERIC LETTER 81-08) for use By letter dated November 4, 1980, we informed you of our requirements stated that a
- of-the ODYN code to calculate pressurization transients,.and of this code would safety evaluation describing the basis for our acceptance be mailed to you inthe near future.
Enloe yuwill 'find a afety evaluation and a supplemental safety evalu-ation which Jointly evaluate the ODYN code and provide information required for application of ODYN.
As you were informed inour letter of November 4, 1980, transient Analyses after performed by. General Electr ic supporting ODYN analyses inreceived reload submittals place of those, February 1, 1981, Must contain appropriate previously performed with REDY for the limiting transients. After January 1982, all operating BWRs with General Electric analyses must have the limiting transients recalculated with the ODYN code, even if no reload submittal has been received. Also, this requirement for the calculation of the limiting transients with the ODYN code is applicable to applicants for an operating license and is a prerequisite to obtaining an operating license.
Sincerely 9 Division ofLicensing En closures:
ljSafety Evaluation 2Supplemental Safety Evaluation cc: w/o enclosure Service List
-Sb 4.2 v--,-
ALL HOLDERS OF CONSTRUCTION PERMITS AND OPERATING LICENSES FOR BOILING WATER REACTORS
SUBJECT:
ODYN CODE (GENERIC LETTER 81-08)
By letter dated November 4, 1980, we informed you of our requirements for use of the ODYN code to calculate pressurization transients, and stated that a safety evaluation describing the basis for our acceptance of this code would be mailed to you in the near future.
Enclosed you will find a safety evaluation and a supplemental safety evalu-ation which Jointly evaluate the ODYN code and provide information required for application of ODYN.
As you were informed in our letter of November 4, 1980, transient analyses performed by General Electric supporting reload submittals received after February 1, 1981, must contain appropriate ODYN analyses in place of those previously performed with REDY for the limiting transients. After January 1982, all operating BWRs with General Electric analyses must have the limiting transients recalculated with the ODYN code, even if no reload submittal has been received. Also, this requirement for the calculation of the limiting transients with the ODYN code is applicable to applicants for an operating license and is a prerequisite to obtaining an operating license.
Sincerely, rrell G-Eisenhut, Director vision of LicenAing DUSTRUBUTTON
Enclosures:
DL Assistant Directors Gray File l) Safety Evaluation ORB BCs -,T. Spels 2 Supplemental Safety Evaluation .-ORB PMs -W. Hodges ORB Licensing Assistant S _A=oe-cc: w/o enclosure OELD (5) M. Hungerbuhler Service List -OI&E 7) N. Hughj NSIC
-1PCEs /S/) £f 7- YJiG2tS2X&E TERA Central File NRC PDR
- SEE PREVIQUS CONCURRENCE Local PDR Y. I I-OFFICE t .DPL*ORB#.2...
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SURNAME# .VRQONEY ....... .I LPRQLITD ....l...INOVAK ........ ..RTE1XESCO ...... ..TSIp.U......... 1GE ISE T... T....
DATE NRC FOR .31....
- C0 a i ________________ ________________ L USOPO: 198O--329.82 NRC FORM 3181410/801 NRCM 0240 O FFICIAL RECORD OFFICIAL R ECO RD COPY C OPY .t USG°O: 1980-32982,
ALL HOLDERS OF CONSTRUCTION PERMITS AND OPERATING LICENSES R BOILING WATER REACTORS
SUBJECT:
ODYN CODE (GENERIC LETTER 81-08)
By letter dated Novenber 4, 1980, we informed you o our requirements for use of the ODYN code to calculate pressurization tran ents, and stated that a safety evaluation describing the basis for our a eptance of this code would be mailed to you in the near future.
Enclosed you will find a safety evaluation d a supplemental safety evalu-ation which Jointly evaluate the ODYT code nd provide information required for application of ODYN.
As you were informed in our letter of Iiventer 4, 1980, transient analyses performed by General Electric supporthg reload submittals received after February 1, 1981, must contain approalate ODYN analyses in place of those previously performed with REDY for limiting me transients. Also, after January 1982, all operating BWRs f th General Electric analyses must have the limiting transients recalcul d with the ODYN code, even if no reload submittal has been received.
Sincerely, Darrell G. Eisenhut, Director Division of Licensing
Enclosures:
Distribution:
1i Safety Evaluatlo DL Assistant Directors 2 Supplemental Sa ety Evaluation ORB BCs ORB PMs cc: Service List /o enclosure ORB Licensing Assistants OELD (5)
/OI&E (7)
/NSIC TERA Central File NRC PDR Local PDR Gray File T. Speis A W.Hodges 4 OFFICEk L RB D- --- D, SURNAME VRoon Nqvak RTed TSpeis Eisenhut DATE / /81 OF CA RECORD 1 88 1/ /81 ..
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lNRC FORM 318 10/80)NRCM 0240 OFtICIAL RECORD) CO 'PY. USOP0: 1980-29482
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BOILING WATER REACTOR LICENSEES . X'^ /XWYs Docket No. 50-293 Docket No. 50-2 Pilgrim Unit 1
- Millstone Unit 1
.Docket No. 50-325
- Docket No. 50-263 Brunswick Unit 1 Monticello Docket No. 50-324 Docket No. 50-133 Brunswick Unit 2 Humboldt Bay Docket No. 50-l0 Docket No. 50-277 Dresden l Peach Bottom Unit 2 Docket No. 50-237 Docket No. 50-278 Dresden 2 Peach Bottom Unit 3 Docket No. 50-249 Docket No. 50-333 Dresden 3 FitzPatrick Docket No. 50-254 Docket No. 50-259 Quad-Cities Unit I Browns Ferry Unit 1 Docket No. 50-265 Docket No. 50-260 Quad-Cities Unit 2 Browns Ferry Unit 2 Docket No. 50-155 Docket No. 50-296 Big Rock Point Browns Ferry Unit 3 Docket No. 50-409 Docket No. 50-271 Lacrosse :- a, Vermont Yankee Docket No. 50-321 Edwin I. Hatch Unit 1
,Docket No. 50-366 Edwin I. Hatch Unit 2 Docket No. 50-331 Duane Arnold Docket No. 50-219 Oyster Creek Docket No. 50-220 Nine Mile Point Unit 1 Docket No. 50-298 Cooper Station vkW'U
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