ML20141E560
| ML20141E560 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 12/20/1985 |
| From: | Opeka J NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | Noonan V Office of Nuclear Reactor Regulation |
| References | |
| AO5390, F0947A, F947A, FO947A, IEIN-84-90, NUDOCS 8601080162 | |
| Download: ML20141E560 (10) | |
Text
g4 m UTILITIES o.n.,o Orric. seio n street. Berkn. Connecticut 9
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H ARTFORD. CONNECTICUT 06141-0270 L
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(203) 665-5000 December 20,1985 Docket No. 50-423 A05390 F0947A Directa of Nuclear Reactor Regulation Mr. V. Noonan, Director PWR Project Directorate #5 Division of PWR Licensing - A U.S. Nuclear Regulatory Commission Washington, D.C. 20555
References:
(1)
- 3. O. Cermak of the WOG letter to D. L. Wigginton of U.S.
NRC, dated October 28, 1985.
(2)
H. L. Thompson memo to E. L. Jordon, IE Information Notice 84-90,
" Main Steam Line Break Effect on Environmental Qualification of Equipment," dated July 15, 1985.
(3)
W.
G. Counsil letter to B. 3. Youngblood, Information Concerning Protection Against Postulated Pipe Breaks Outside Containment, dated June 20, 1984.
(4) WCAP-10961-P, "Steamline Break Mass / Energy Releases for Equipment Environmental Qualification Outside Containment," Report to the WOG HELB/SBOC Subgroup, dated October 1985.
Dear Mr. Noonan:
Millstone Nuclear Power Station, Unit No. 3 Evaluation of Environmental Effects of Main Steam Line Break Outside Containment In June 1984, all Westinghouse utilities were notified of a potential unreviewed safety question concerning the impact of release of superheated steam from the postulated Main Steam Line Break (MSLB) on the Environmental Qualification (EQ) of the equipment located outside containment. Northeast Nuclear Energy Company (NNECO)is a member of the Westinghouse Owners Group (WOG) High Energy Line Break (HELB)/Superheated Blowdown Outside Containment (SBOC)
Subgroup. This subgroup was formed to address the impact of superheated blowdowns from HELBs outside containment on the EQ of the equipment located in the vicinity of the break. In Reference (1) the WOG informed the NRC of the completion of the program. A final report detailing the results (mass / energy releases) of the program was issued to each participating utility member on 8601000162 851220 an J. Knight (ltr only)
PDR ADOCK 05000423 EB (BALLARD)
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FOB (BENAROYA)
0 October 21, 1985. NNECO received the implementation guidelines which are necessary to perform plant-specific equipment EQ evaluation from the TOG on November 4,1985.
The design basis for postulating a MSLB is in accordance with NRC Standard Review Plan (SRP) Branch Technical Position (BTP) MEB 3-1 and ASB 3-1.
BTP MEB 3-1 describes requirements for postulating rupture locations for high and -
moderate energy lines. BTP MEB 3-1 further states that breaks and cracks need not be postulated in certain portions of a piping system provided specific ASME III Code requirements and stress and f atigue limits have been met. These areas are termed break exclusion areas. Portions of the Millstone Unit No. 3 main steam system extending from the containment wall past the Main Steam Isolation Valves (MSIV) to the Main Steam Valve Building (MSVB) F-line wall (first rupture restraint outside containment) are classified as break exclusion areas. Contrary to this, BTP-ASB 3-1 states that even though portions of the main steam system meet this break exclusion criteria, a break of at least one square-foot must be postulated for determining environmental effects for equipment qualification. Therefore, a MSLB has been considered in the break exclusion area between the containment wall and the MSIV for development of temperature profiles for equipment environmental qualification.
No single active f ailure has been assumed, since per ASB 3-1 a single failure is assumed in conjunction with a postulated piping failure.
Since oiping failure need not normally be postulated in the break exclusion areas as defined in MEB 3-1 no concurrent single active failure is assumed when determining the resulting environmental cf fects. This is consistent with the NRC position on this issue (Reference (2)).
The temperature transients in the MSVB following a main steam line pipe rupture were determined using the same method of analysis and building model described in Reference (3). A maximum rupture size of 1.0 square-foot was postulated consistent with BTP ASB 3-1. A spectrum of rupture sizes up to 1.0 square-foot was considered. The mass and energy release data in WCAP 10961, Tables A-
' l.54 through 58 (Reference (4)) were determined to be the appropriate data for Millstone Unit No. 3.
2 2
2 The calculated pressure and temperature profiles for a 1.0 f t, 0.8 f t, 0.6 f t i
and 0.4 f t2 steamline break are shown in Figure I and 2 respectively. A 0.2 f t break was not analyzed since the release data indicated that tube uncovery and the resulting superheated steam will not occur. The above information satisfies License Condition 2.C(3) of the Millstone Unit No. 3 Operating License, NPF-44.
The potential effects of the increased temperature on equipment required to safely shutdown the plant and maintain it in a safe shutdown condition are being evaluated at this time and willinclude the following elements:
o identify safety-related equipment and determine if equipment operation is required.
o Identify EQ envelope for each piece of equipment required to operate.
o Compare new temperature profiles to the equipment qualification levels.
. o Resolve any EQ conflicts identified and determine course of actions.
We will provide the Staff with a status report on the evaluation of environmental effects on equipment required to safely shut down the plant and maintain it in a safe shut-down condition by January 6,1986.
If there are any questions, please contact our licensing representative directly.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY et. al.
BY NORTHEAST NUCLEAR ENERGY COMPANY Their Agent i F. GA
- 3. F. ObeWa U
Senior Vice President STATE OF CONNECTICUT )
) ss. Berlin COUNTY OF HARTFORD
)
Then personally appeared before me 3. F. Opeka, who being duly sworn, did state
'that.he is Senior Vice President of Northeast Nuclear Energy Company, a Licensee _ herein, that he is authorized to execute and file the foregoing information in the name and on behalf of the Licensees herein and that the statements contained in said information are true and correct to the best of his knowledge and belief.
AA&M A l hM Motary Publif iMy Comm:ssion Expires March 31,1938
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