ML19269C739
| ML19269C739 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 01/30/1979 |
| From: | Counsil W NORTHEAST UTILITIES |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| References | |
| TASK-05-11.A, TASK-5-11.A, TASK-RR NUDOCS 7902120137 | |
| Download: ML19269C739 (4) | |
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January 30, 1979 Docket No. 50-245 Director of Nuclear Reactor Regulation Attn: Mr. D. L. Ziemann, Chief Operating Reactors Branch #2 U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Reference:
(1)
D. L. Ziemann letter to W. G. Counsil dated December 21, 1978.
Gentlemen:
Millstone Nuclear Power Station, Unit No. 1 Systematic Evaluation Program (SEP)
High/ Low Pressure System Isolation In Reference (1), the NRC Staff forwarded to Northeast Nuclear Energy Company (NNECO) a listing which presented information on the above-subject SEP topic. UNECO was requested to verify the correctness of the data in that table.
In accordance with that request, NNECO has reviewed the NRC Staff prepared listing. As a result of that review, a number of substantive changes have been made; these are indicated in the attachment.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY
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1 W. G'. 'Counsil Vice President Attachment es 790212o Mi s
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ATTACHMENT SYSTEMATIC EVALUATION PROGRAM (SEP)
TOPIC V-II.A HIGH/ LOW PRESSURE SYSTEM ISOLATION JANUARY, 1979
PL#4T: Millstone Unit 1 Evaluation of Isolation of Low Pressure Systems From Reactor Coolant System Meets Redundancy Testable Location of Method of Isolation of Type Between HP/LP Check Valve Pressure Method of Direct Interfaces *4 Criteria Isolation Valves Valves Interface Orienta tion Reduction Isolation Remarks 3
Water Cleanup System 6 Pressure Pressure Group 3 Fig X-2.3 (FSAR) Cleanup E
Inlet Yes 2M0 Yes Control NA Control Isolation
- system automatically shut-Valve Valve down and isolated on low flow, high pressure or high temperature.
Discha rge Yes IMO &
No Recirc Pump Horizontal
'iA Group 3 Relief valves provided in 1 Check Discharge Isolation
- low pressurc portion Valve ECCS Low Pressure Yes IMO &
No Test Valve Horizontal NA Normally Fig. VI-2.6 FSAR - discharge Injection 1 Check Outside (BothLines) closed only cnly, suction in suppression Valve Drywell initiated pool. Relief Valves provided (Beyond In-on ECCS jection Valve) signal Yes IMO &
No Test Valve Horizontal NA Normally Fig. VI-2.2 FSAR - discharge LowPgessureCore Spray 1 Check Outside (Both Lines) closed only side only, suction in Valve Drywell initiated suppression pool. Relief (Beyond In-on ECCS valves provided.
jection Valva) signal Sampling System Yes 2 Sole-Yes Control Valve NA Control Group 1 No information provided in noid dalve Isolation
- FSAR. Relief valve provided valves RHR System Suction side Yes 2MO Yes NA NA NA Group 3 High pressure system Isolation
- Pumps Trip on T>350*F Cischarge Side Yes 2MO Yes NA NA NA Group 3 Permissive prevents from Isolation
- operating if temp. > 350T and suction press. > 4 psig F eactor V essel Head Yes Yes IMO &
No NA Horizontal
.( A Group 3 High pressure system down-Spray Cooling 1 Check Isolation
- stream of pumps. Potential for overpressurizing conden-sate storage tank does not exist as there are 2 check valves and pump discharge pressure exceeds reactor pressure.
- fefer to Tech. Spec. Table 3.7.1
NOTE:
- 1. PWRs only
- 2. BWRs only
- 3. Only direct interfaces considered--service water and component cooling water systems not evaluated
- 4. High pressure systems (i.e., control rod drive hydraulic, isolation condenser, standby liquid control, high pressure injection, & RCIC) connected to reactor coolant pressure boundary not evaluated
- 5. Inadvertent overpressurization of makeup tank due to reactor coolant pump seal ?eak off
- 6. Reactor water cleanup system for BWRs and CVCS or Letdown System for PWRS 7., Isolation requirements for ECCS specified in SRP 6.3 (Section III), for RHR system in BTP RSB 5-1 attached to SRP 5.4.7 and for water cleanup and sampling system in GDC 55
- 8. NA - Not Applicable
- fefer to Tech. Spec. Table 3.7.1