ML20203B074
| ML20203B074 | |
| Person / Time | |
|---|---|
| Site: | Mcguire |
| Issue date: | 12/05/1997 |
| From: | Rinaldi F NRC (Affiliation Not Assigned) |
| To: | Barron H DUKE POWER CO. |
| References | |
| TAC-MA0143, TAC-MA143, NUDOCS 9712120326 | |
| Download: ML20203B074 (4) | |
Text
.. _.
ch 5, W Mr. H. B. Barron Dukibullom FRin:Idi Vice Pr:sident, McGuira Site
'90tMff!P' OGC Duke Energy Corporation PUBLIC cog',], Rll 12700 Hagers Ferry Road PD 112 Rdg.
WBeckner Huntersville, North Carolina 28078 8965 BBoger ACRS HBerkow JJohnson, Ril LBerry
SUBJECT:
REVISED DESIGN BASIS ANALYSIS FOR LICENSE AMENDMENT NO.156 FOR MCGUIRE NUCLEAR STATION, UNIT 2 (TAC NO. MA0143)
Dear Mr. Barron:
Dy letter dated January 6,1997, as revised by letters dated April 10 and 15,1997, you requested NRC approval for a one-time change to the McGuire Units 1 and 2 Technical Specifications (TS) that would allow operation of the Containment Purge Ventilation System in Modes 3 and 4 during the start up following the steam generator replacement outages. You stated that the approval was needed to protect workers from airbome hazardous materials while making containment entries during the initial start up with the new steam generators.
NRC approval was granted by Amendments 174 (Unit 1), and 156 (Unit 2), dated April 24, 1997. In evaluating the impact of these TS changes on the radiological consequences of the limiting design basis accident (loss of coolant accident), you committed to a minimum source term decay time of 70 days.
By letter dated November 21,1997, you requested NRC's 6pproval to change the design basis analysis that supported the April 24,1997, amendments. Due to schedule improvements in the steam generator replacement outage, you may be ready to enter Mode 4 in as little as 65 days.
The staff has reviewed your request, and reanalyzed the expected offsite and control room doses resulting from a postulated loss of coolant accident (LOCA) using the reduced (65-day) decay time. The enclosure compares the results of the original analysis, as documented in the Safety Evaluation issued with the April 24,1997, license amendments, with tim revisod analysis using 65 days of radiological decay.
The reduced decay timo recults in an increase in the radiological consequences of a postulated design basis LOCA. However, since you have committed to providing eye protection from beta radiation for the control room operators during a LOCA, the consequences are within the acceptance criteria of the Standard Review Plan. Therefore, the staff finds that the request to enter reactor Modes 3 or 4 as early as 65 days post-reactor shutdown is acceptable, Sincerely, D(*g ORIGINAL SIGNED BY:
l Frank Rinaldi, Project Manager l
Project Directorate 112
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9712120326 971205 Division of Reactor Projects l/II
\\
DR ADOCK 05 30 Office of Nuclear Reactor Regulation p
)) ][ ]KR ff)lMf i
Docket No. 50 370
Enclosure:
As stated cc w/sncl: See next page To receive a copy of this document, Indicate in the box:. C" = Copy without attachment / enclosure "E" o Copy with attachment / enclosure "N" = No copy l
OFFICE-PM:PDil 2Q (
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NAME FRinaldi:en /'
LBerry V/h HBerilow -
DATE M/97 il/ Q/97 1
11/ti /97
/ /97
/ /97
/ /97 DOCUMENT NAME: G:\\MCGUIRE\\ MAO 143.LTR OFFICIAL RECORD COPY
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t UN11ED STATES y
NUCLEAR REQULATORY COMMISSION WASHINGTON, D.C. 300tH001 December' 5, 1997 Mr. H. B. Barron Vice President, McGuire Site Duke Energy Corporation 12700 Hagers Ferry Road Huntsisville, North Carolina 28078-8985
SUBJECT:
REVISED DESIGN BASIS ANALYSIS FOR LICENSE AMENDMENT NO.156 FOR MCGUIRE NUCLEAR STATION, UNIT 2 (TAC NO. MA0143)
Dear Mr. Barron:
By letter dated January 6,1997, as revised by letters dated April 10 and 15,1997, you requested NRC approval for a one time change to the McGuire Units 1 and 2 Technical Specifications (TS) that would allow operation of the Containment Purge Ventilation System in Modes 3 and 4 during the start up following the steam generator replacement outages. You stated that the approval was needed to protect workers from airborne hazardous materials while making containment entries during the initial start up with the new steam generators.
NRC approval was granted by Amendments 174 (Unit 1), and 156 (Unit ?), dated April 24, 1997. In evaluating the impact of these TS changes on the radiological consequences of the limiting design basis accident (loss of-coolant accident), you committed to a minimum source term decay time of 70 days.
By letter dated November 21,1997, you requested NRC's approval to change the design basis analysis that supported the April 24,1997, amendments. Due to schedule improvements in the steam generator replacement outage, you may be ready to enter Mode 4 in as little as 65 days.
The staff has reviewed your request, and reanalyzed the expected offsite and control room l
doses resulting from a postulated loss-of coolant accident ('.OCA) using the reduced (65-day) decay time. The enclosure compares the results of the original analysis, as documented in the Safety Evaluation issued with the April 24,1997, license amendments, with the revised analysis using 65 dayc of radiological decay.
l The reduced decay time results in an increase in the radiological consequences of a pastukted i
design baals LOCA. However, since you have committed to p.oviding eye protection from beta radiation for the control room operators during a LOCA, the consequences are within the acceptanco critsria of the Gtandard Review Plan. Therefore, the staff finds that the request to enter reactor Modes 3 or 4 as early as 65 days post-reactor shutdown is acceptable.
Sincerely, fU Frank Rinaldi, Project Manager Project Directorate ll 2 Division of Reactor Projects - 1/II
- Off'ce of Nuclear Reactor Regulation Docket No. 50-370
Enclosure:
As stated cc wIencl: See next page -
i McG' aire Nuclear Station cc:
Mr. Paul R. Newton Ms. Karen E. Long i
Legal Department (PB05E)
Assistant Attorney General Duke Energy Corporation North Carolina Department of 422 South Church Street Justice Charlotte, North Carolina 28242 P. O. Box 62g Raleigh, North Carene Nfd County Manager of Mecklenburg County Mr, G. A. Copp 720 East Fourth Street Licensing ECO' Charlotte, North Carolina 28202 Duke Energy C, wration 526 South Chu ti Strem Michael T. Cash Charlotte, Nort CS/ch % 2h N 2 Regulatory Compliance Manager Duke Energy Corporation Regional Adi +wmor, Rogivn !!
McGuire Nuclear Site U.S. Nuclear h mlvoty Commluhn 12700 Hagers Ferry Road Atlanta Federal ' 'et Huntersvill6, North Carolina 28078 61 Forsyth Street,,. '*L Sui e MT RS t
/,tlanta, Georgia 303W J. Michael McGarry, Ill, Esquire Winston and Strawn Elaine Wathei J ' C N nne 1400 L Street, NW.
Division of Er
'm c., M4ansmsa Washington, DC 20005 116 West Jonew.% >
Raleigh, North Carr e tTOUS '
Senior Resident inspector c/o U.S. Nuclear Regulatory Mr. Richard M. Fry, m '.x Commission Division of Radiation.
^
12700 Hagers Ferry Road North Carolina Departmen1 of Huntersville, North Carolina 28078 Environment, Health and Natural Resources Mr. Peter R. Harden, IV 3825 Barrett Drive Account Sales Manager Raleigh, North Carolina 2760g 7721 Westinghouse Electric Corporation Power Systems Field Sales Mr. T. Richard Puryear P.O. Box 7288 Owners Group (NCEMC)
Charlotte, North Carolina 28241 Duke Energy Corporation 4800 Concord Road Dr. John M. Barry York. South Carolina 2g745 Mecklenberg County Department of Environmental Protection 700 N. Tryon Street Charlotte, North Carolina 28202
____._._.~._..
o McGuire Nuclear Station. Unit 2 Revised Radiological Consequences of a LOCA While Purging Containment Following the Steam Generator Replacement Outage QQae (Rem)
Acceptance 70 Davs 65Eaxa cnteria Exchal^n Area Boundarv (2 Hours):
WIole Body
.053
.066 25 1
- Thyroid 70 108 300 I
LQWEopulatiorLZQDe (30 Dwn):
Whole Body
.018
.022 25 Thyroid 18 28 300 Control kQQ'n.(30SJVM; Whole Body
.014
.017 5
c Thyroid 6.6 10.1 30 Skin 30 31 30(75')
- 75 rem applicable with eye protection provided.
Enclosure