ML18094B235
| ML18094B235 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 01/04/1990 |
| From: | Miller L Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18094B236 | List: |
| References | |
| NLR-90006, NUDOCS 9001180420 | |
| Download: ML18094B235 (6) | |
Text
OPS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station January 4, 1990 NLR-90006 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
REQUEST FOR DISCRETIONARY ENFORCEMENT TECHNICAL SPECIFICATION 3.0.3 AND 3.5.2 ACTION (C)
FACILITY OPERATING LICENSE DPR-75 SALEM GENERATING STATION UNIT NO. 2 DOCKET NO. 50-311 Public Service Electric and Gas Company:(PSE&G) hereby requests discretionary enforcement from Technicai Specification Action Statements 3.0.3 and 3.5.2(c) for Salem Unit 2.
Specifically, we are requesting an additional 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> beyond the 7 hour8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> requirement to be in Hot Standby per 3.0.3 and 3.5.2 ACTION (c).
The requested relief would provide us the opportunity to stabilize the Unit at its current power level of approximately 60% in anticipation of the issuance of a waiver of compliance for Technical Specification 4.5.2.h.2.b which would allow us to exit 3.0.3 and 3.5.2 ACTION (c).
The attached document is a draft of our emergency technical specification change request for Technical Specification 4.5.2.h.2.b which we will be submitting to NRC-NRR shortly.
Your timely assistance in this matter is requested in order to avert a plant shutdown currently planned for 4:30 PM.
If you have any questions, please contact us.
~--~T~h.e_Eo_erm1_e_e_o_0Je~-----
(
9001180420 900104 I
PDR ADOCK 05000311 P
PDC Sincerely,
- ~
L:. K. Miller General Manager -
Salem Operations 95-2189 (SM) 12-88
Document Control Desk NLR-90006 C
Mr. J. C. Stone Licensing Project Manager Ms. K. Halvey Gibson Senior Resident Inspector Mr. W. T. Russell, Administrator Region I Mr. Kent Tosch, Chief New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 4.15 Trenton, NJ 08625
NLR-90005 ATTACHMENT 1 EMERGENCY LICENSE AMENDMENT REQUEST FACILITY OPERATING LICENSE DPR-75 SALEM GENERATING STATION -
UNIT NO. 2 DOCKET NO. 50-311 I.
Description of Proposed Change The proposed change would add a footnote to Surveillance Requirement 4.5.2.h.2.b stating that a one time waiver of the 550 gpm maximum flow requirement is in place from January 4, 1990 until eGameReeme~- ef the Unit 2 Fifth Refueling outage.
~~~~s~
II.
Reason for Proposed Change During ~=oA13~d!:;; =W~s~~
eeReerns ~egarding ECCS fl:ew inconsistencies, an error was found
~
in the ECCS flow calculations for the current fuel cycle.
When f,:
the error was corrected, the total pump flow rate was in excess of the value allowed by TS surveillance requirement 4.5.2.h.2.b.
This has resulted in declaring both trains of ECCS inoperable and entering specification 3.0.3.
This emergency license amendment is therefore required to prevent shutdown of SGS unit 2.
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.
PSE&G has previously evaluated similar conditions at Unit 1 in LER 89-020-00 dated June 14, 1989.
The conditions analyzed in the
NLR-90005 2 -
Unit 1 LER were on the order of 15% in excess of the 550 gpm requirement.
The existing conditions at Unit 2 are on the ord*
of 1% in excess of the 550 gpm limit.
As a result;Gff the Unit analysis bounds the existing Unit 2 conditions.
Cavitation would result from the loss of ~nsufficient suction tJt>sH pre~sure to the pump.
The required &u.eG~on pres&dta for the
~
flow is i:A enmss G'f 23 feet'dbwat:ec tteaei (;;!3 ft. at sse
~
For accident conditions, the minimum possible RWST tank 1_:vel re~ched would.be at 15~24 feet* 'WAich corraspends to fl.0 fee/+~~ifftlt. *suet iota pressQre.
At this minimum RWST ta1 level, suction is re-aligned to the discharge of the RHR pumps during ECCS actuation.
Tbe diseba~~e pressu1e cottesponas to 3t ieet of bead during reoire\\ilat:ien.
The minimum.s;,uction pressure available to the ~entrifugal Charging Pumps would occur just before re-alignment with the RWST at 15 feet.
This is~ more than what is required for maximum flow at 550 gpm.
The increase I~.
flow represents a,..c;1% increase in discharge rate compared with a
~% increase in ~e~ieft pzoseare.
~~%
~~SH The increased flow rate would place a higher load requirement on the pump motor.
Since the motors of the Unit 1 pumps were determined to be sized to accommodate the increased flow rate, a similar conclusion can be made for the Unit 2 motors since the flow increase is smaller and the Unit 2 motors are identical in1 design to the Unit 1 motors.
The increased horse power required to produce the increased flow would place an additional load on the emergency D/Gs.
Since the increased load for the Unit 1 conditions would not exceed the allowable 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> continuous load rating, a similar conclusion can be made for the Unit 2 conditions since the flow increase is smaller.
NLR-90005 3 -
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'4i~forcem&Rt aisere~ion provides a safer course of action than imposing an unnecessary transient to shut down the plant.
IV.
Significant Hazards Consideration Evaluation The proposed change to the SGS Technical Specifications:
- 1.
Does not involve a significant increase in the probability
~
consequences of an accident previously evaluated.
(J('
Based on evalYatioa of t~ccs system, the affected Unit 2 systems and components would be able to perform their intended safety functions during operation under existing conditions.
We therefore believe that operating with existing ECCS conditions until the beginning of the Fifth Unit 2 Refueling Outage would not adversely affect public health and safety and would not increase the probability or consequences of a previously analyzed accident.
- 2.
Does not create the possibility of a new or different kind of accident from any accident previously evaluatedo The proposed change impacts a plant operating-parameter associated with the ECCS system; however, since all ECCS equipment can perform its intended safety function while operating with the modified ECCS pump parameter, operation
NLR-90005 4 -
on a temporary basis with the modified parameter will not create the possibility of a new or different kind of accident.
- 3.
Does not involve a significant reduction in a margin of safety.
As discussed previously, all ECCS components would be able to perform their intended safety functions during operation under existing conditions.
We therefore conclude that no safety margin will be significantly reduced while operating under existing ECCS conditions.
- v.
Conclusion As discussed in Item IV above, PSE&G has concluded that the proposed change to the Technical Specification does not involve a Significant Hazards Consideration since the change (i) does not involve a significant increase in the probability or consequences of a previously analyzed accident, Iii) does not create the possibility of a new of different kind of accident, and (iii) does not involve a significant reduction in a margin of safety.