ML18092B174
| ML18092B174 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/27/1986 |
| From: | Fischer D Office of Nuclear Reactor Regulation |
| To: | Corbin McNeil Public Service Enterprise Group |
| References | |
| NUDOCS 8606120734 | |
| Download: ML18092B174 (6) | |
Text
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Docket Nos. 50-272 and 50-311 Mr. C. A. McNeill, Jr.
Vice President - Nuclear May 27, 1986 D TRIBUTION ocket Fi e L PDR PAD#3 Rdg H. Thompson D. Fischer NRC PDR Gray File J.Gibson OELD Public Service Electric and Gas Company Post Office Box 236 E. Jordan J. Partlow N. Thompson C. Vogan B. Grimes ACRS 10 Hancocks Bridge, New Jersey 08038
Dear Mr. McNeill:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - TECHNICAL SPECIFICATION CHANGES FOR BORON INJECTION TANK REMOVAL The staff has reviewed the information submitted in your request to remove the Boron Injection Tank, dated October 25, 1985.
The staff has concluded that insufficient information was provided to complete the evaluation.
The additional information required is discussed in the enclosures.
Please respond to this request for information within 60 days from receipt of this letter.
The reporting and/or recordkeeping requirements of this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
Enclosures:
As stated cc w/enclosures:
See next page Sincerely,
/s/DFischer Donald C. Fischer, Senior Project Manager PWR Project Directorate No. 3 Division of PWR Licensing-A DATE : 5/'f'\\/86
- 5/i-7 /86
- 5/
ICIAL RECORD COPY 8606120734 960527 PDR ADOCK 05000272 p*
Mr. C. A. McNeill Public Service Electric & Gas Company Salem Nuclear Generating Station cc:
Mark J. Wetterhahn, Estjuire Conner and Wetterhahn Suite 1050 1747 Pennsylvania Avenue, NW Washington, DC 20006 Richard Fryling, Jr., Esquire Assistant General Solicitor Public Service Electric & Gas Company P. O. Box 570 - Mail Code TSE Newark, New Jersey 07101 Gene Fisher, Bureau of Chief Bureau of Radiation Protection 380 Scotch Road Trenton, New Jersey 08628 Mr. John M. Zupko, Jr.
General Manager - Salem Operations Public Service Electric & Gas Company Post Office Box E Hancocks Bridge, New Jersey 08038 Robert Traae, Mayor Lower Alloways Creek Township Municipal Hall Hancocks Bridge, New Jersey 08038 Thomas Kenny, Resident Inspector Salem Nuclear Generating Station U.S. Nuclear Regulatory Commission Drawer I Hancocks Bridge, New Jersey 08038 Richard F. Engel Deputy Attorney General Department of Law and Public Safety CN-112 State House Annex Trenton, New Jersey 08625 Frank Casolito, Action Chief Bureau of Radiation Protection Department of Environmental Protection 380 Scotch Road.
Trenton, New Jersey 08628 Richard B. McGlynn, Commission*
Department of Public Utilities State of New Jersey 101 Commerce Street Newark, New Jersey 07102 Mr. David Wersan Assistant Consumer Advocate Office of Consumer Advocate 1425 Strawberry Square Harrisburg, Pennsylvania 17120 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406 Lower Alloways Creek Township c/o Mary 0. Henderson, Clerk Municipal Building, P.O. Box 157 Hancocks Bridge, New Jersey 08038 Mr. Bruce A. Preston, Manager Licensing and Regulation Public Service Electirc & Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038
ElosURE 1 REQUEST FOR ADDITIONAL INFORMATION TECHNICAL -SPECIFICATION CHANGES REGARDING SALEM 1 & 2 BORON INJECTION TANKS (BITS)
REACTOR SYSTEMS BRANCH
- 1.
For the large steam line break accident, please provide the minimum DNBR calculated assuming both present conditions (BIT boron concentration of 20,000 ppm) and proposed condition (BIT boron concentration 0 ppm).
In accordance with the regulations of 10 CFR 50.92, the staff requires this information to detennine whether a significant reduction in margin of safety is involved.
- 2...Page 3 of yo~r submittal.states:
"The heat tracing will be deleted and the BIT will be maintained at a boron concentration* between 4 weight %
and 0 weight %n.
Therefore assured means.would still be raquired to maintain the fluid inside the BITS and associated SI piping at a minimum of 65°F (the minimum solution temperature of 4% boric acid). State how this will be accomplished *.
- (Note: We assull)e you mean boric acid concentration.)
- 3.
The Salem FSAR apparently does not corytain detailed piping and instrumentation drawings of the SI piping from the charging pumps via the BITs to containment penetration.
We also can not find the BIT location in the building drawings (i.e., Figures 3.6-26, 3.6-27 and 6.3-1 do not provide sufficiently detailed information). Therefore, please provide detailed piping and instrumentation schematics and layout drawings for the above flow path.
(The latter could simply consist of a marked up building drawing.) *Also, state whether the connections to the Boric Acid Tank BAT and other concentrated boric acid sources will be blanked off.
- 4.
Provide assurance that periodic sampling of the BIT and connected SI piping will be conducted to determine boron concentration. Also, discuss whether the Salem plant procedures will include requirements for periodic flushing of the BIT and connected S1 lines.
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- 5.
FSAR Figure 10.3-1 does not show check valves in the main steam lines.
Are the main steam stop valves designed to provide positive flow isolation for both forward and reverse flow?
- 6.
State what investigations have been made reparding the effect of the proposed decrease in the BIT boron concentration on the amount of superheat resulting from a steam line break, including the effect on equipment that can be affected by the superheated steam, which may subsequently react in such a way as to increase the severity of the accident.
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~OSURE 2 REQUEST FOR ADDITIONAL INFORMATION TECHNICAL SPECIFICATION CHANGES REGARDING BORON INJECTION TANK (BIT)
SALEM UNITS 1 AND 2 DOCKET NOS. 50-272/311-ENGINEERING BRANCH DIVISION OF PWR LICENSING-A
- 1.
State the values of re-voporization coefficient that were used in in the main steam line break analyses. Provide justification for using values that are larger than eight (8) percent.
2 *. * "Discuss briefly why a different number of blowdown cases and break
- sizes were evaluated in the revised containment pressure/temperature anaylses for the proposed reduction in BIT boron concentration.
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"LOSURE 3 SALEM UNITS 1 AND 2 REQUESJ FOR ADDITIONAL INFORMATION REGARDING BORON INJECT°ION TANK PLANT SYSTEMS BRANCH.
Ql:
With respect to the analyses presented in reference 1, ~upporting removal of the Boron Injection Tank (BIT), the mass and energy releases following a main steam line break were calculated using the Westinghouse computer code LOFTRAN.
The version of the LOFTRAN code used does not account for heat transfer to the steam during steam generator tube bundle uncovery. This heat transfer effect will lead to superheating of the steam being produced..
- i~ the steam generator, and the exiting steam temperature may be substan-tially above the qualification temperature of equipment.
The phenomenon of steam superheating and its effect on conta.inment respons~ has not been*
addressed in the main steam line break analyses that ha~e been submitted.
I Provide a blowdown anaiysis which includes steam superheating effects.
Discuss and justify the assumptions and conservatisms made relative to containment response analysis.
Q2:
The analyses presented.in reference 1 did not address the effect of BIT removal on safety related equipment outside containment. Provide an analysis of the environmental conditions outside containment which includes the steam superheating effect discussed in the preceeding question. Discuss and justify the adequacy of.the qualification of all safety related equipment outside containment that may be exposed to the superheated steam blowdown.
References:
- 1. Letter from Corbin McNeill, Jr. (Public Service Electric and Gas*company) to Steven Varga {NRC), dated October 25, 1985.
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