ML18094B346
| ML18094B346 | |
| Person / Time | |
|---|---|
| Site: | Salem |
| Issue date: | 03/09/1990 |
| From: | Miltenberger S Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NLR-N90051, NUDOCS 9003220163 | |
| Download: ML18094B346 (5) | |
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Public Service Electric and Gas Company Steven E. Miltenberger Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1100 Vice President and Chief Nuclear Officer MARO 9 W90 NLR-N90051 Supplement to LCR 90-02 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
SUPPLEMENT TO EMERGENCY LICENSE AMENDMENT REQUEST 90-02 TECHNICAL SPECIFICATION 3.5.2 FACILITY OPERATING LICENSE DPR-75 SALEM GENERATING STATION UNIT NO. 2 DOCKET NO. 50-311 This letter supplements Emergency License Change Request (LCR) 90-02, dated January 4, 1990.
This supplement is being submitted to update and correct information provided in the original LCR.
The updated information does not impact the basis for our conclusions relative to our no significant hazards determination; the original significant ha-zards analysis remains valid.
An updated justification section is included in Attachment 1 of this submittal and is intended as a replacement for the justification section submitted in Attachment 1 of our original submittal.
In accordance with the requirements of 10CFR50.91(b) (1), a copy of this request has been sent to the state of New Jersey as indicated below.
Should you have any questions, please do not hesitate to contact us.
Affidavit Attachment Sincerely, 11001 1/1
Document Control Desk NLR-N90051 c
Mr. J. c. Stone Licensing Project Manager Mr. T. Johnson Senior Resident Inspector Mr. w. T. Russell, Administrator Region I Mr. Kent Tosch, Chief I
New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 W\\R O 9 1990
REF: NLR-N90051 supplement to LCR 90-02 STATE OF NEW JERSEY
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SS.
COUNTY OF SALEM
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- s. Miltenberger, being duly sworn according to law deposes and says:
I am Vice President and Chief Nuclear Officer of Public Service Electric and Gas Company, and as such, I find the matters set forth in our letter dated MAR 0 9 7990', 1990, concerning the Salem Generating Station, Unit No. 2, are true to the best of my knowledge, information and belief.
Subscribed and Sworn to before me this 0/-1; day of C/J{kl~, 1990
. ~:ii/JJ Y'Ji.~,4/UJ No~ary Public of New Jersey WiMiT!l M. filARSHti!.l NOTARY. Pi.JDUC OF NEW JERSEY My Commission expires on ~~~~-M_v_c_o_m_m_1s_sl_n~_E_~~'~_lra_s_~_!a~y~6~*~1=g=-g3
ATTACHMENT 1 SUPPLEMENT TO LICENSE AMENDMENT REQUEST FACILITY OPERATING LICENSE DPR-75 SALEM GENERATING STATION -
UNIT NO. 2 DOCKET NO. 50-311 NLR-90051 SUPPLEMENT TO LCR 90-02 The following justification section is intended as a replacement for the justification section submitted in our original amendment application (LCR 90-02) on January 4, 1990.
III. Justification for Proposed Change Operation with existing ECCS conditions will not place the plant in an unsafe condition.
PSE&G believes that there is ample technical justification for the requested relief.
Cavitation would result if the available net positive suction head (NPSH) were less than the required NPSH during a transient.
The required NPSH at 550 gpm is 23 feet as referenced in Table 6.3-13 of the Salem UFSAR.
The required NPSH at 555 gpm is estimated to be 24 feet based on extrapolation of the pump performance curve.
For a design basis accident, it is assumed that both charging/SI pumps (555 gpm per pump), both safety injection pumps (650 gpm per pump), and either both RHR pumps (3000 gpm per pump) or one RHR pump (4500 gpm) are operating during the injection phase of the accident as indicated in Table 6.3-13 of the Salem UFSAR.
At the 15.24 feet RWST level, manual and automatic actions are initiated in accordance with Table 6.3-6 of the Salem UFSAR.
It is estimated that the lowest level in the RWST prior to shutting down the centrifugal charging pumps is approximately 3 feet.
At this level, the available NPSH at 555.gpm is calculated to be 32 feet.
NLR-N90048
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LCR 90-02, Revision 1 Extrapolation for the minor flow increase of 5 gpm is considered reasonable.
The pump vendor has concurred to the validity of extrapolation for minor flow increases such as 5 gpm.
Generally, the pump vendor conservatively specifies the pump runout limit to include some margin from the actual runout limit as determined from testing.
Based on the above analysis, the available pump NPSH exceeds the required NPSH by 8 feet at the lowest RWST level and at a flow rate of 555 gpm.
The increased flow rate of 555 gpm does not result in increased brake horsepower as determined from the pump performance curve.
The actual motor loading at 555 gpm, when added to the other diesel generator loads in Salem UFSAR Table 8.3-3, is well below the 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> rating of 2750 KW for the emergency diesel generators.
The expected increased flow to the RCS during postulated ECCS injection and recirculation phases would not impact the cooling function of the system.
We therefore conclude that, with the existing conditions, the affected Unit 2 systems and components would be able to perform their intended safety functions, and temporary operation under existing conditions would not adversely affect the health and safety of the public.
Furthermore, we believe that an emergency license change provides a safer course of action than imposing an unnecessarily severe transient to shut down the plant.