ML17056B044
| ML17056B044 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 10/11/1990 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17056B045 | List: |
| References | |
| NUDOCS 9010240079 | |
| Download: ML17056B044 (10) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 NIAGARA MOHAWK POWER CORPORATION DOCKET NO. 50-410 NINE MILE POINT NUCLEAR STATION UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 22 License No. NPF-69 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Niagara Mohawk Power Corporation (the licensee) dated July 19, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the,Act) and the Commission's rules and regulations set forth in 10 CFR Chapter 1;
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will 'not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-69 is hereby amended to read as follows:
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9010240079 901011 PDR ADOCK 05000410 P
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached
- hereto, as revised through Amendment No. 22 are hereby incorporated into this license.
Niagara Mohawk Power Corporation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance to be implemented within 30 days.
Attachment:
Changes to the Technical Specifications FOR THE NUCLEAR REGULATORY COMMISSION m,awe. C~
Robert A. Capra, Director Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Date of Issuance:
October ll, 1990
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e UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.
22 TO FACILITY OPERATING LICENSE NO. NPF-69 DOCKET NO. 50-410 Revise Appendix A as fo11ows:
Remove Pa e
3/4 6-27 3/4 6-35 Insert Pa e
3/4 6-2?
3/4 6-35
TABLE 3.6.3-1 (Continued)
PRIMARY CONTAINMENT ISOLATION VALVES ISOLATION VALVE NO.
VALVE FUNCTION VALVE ISOLATION GROUP SIGNAL(a)
MAXIMUM CLOSING TIME (SECONDS) m 2RHS"HOV142(j)(m) 2RHS'MOV149(j)(m) 2RHS*SOV35 A/B (j)(m)
I 2RHS*SOV36 A/B (j)(m) 2RDS'AOV124(IQ) 2RDS*AOV132(k) 2RDS*AOV123(IQ) 2RDS*AOV130(IQ)
SCRAM Discharge Volume Vent SCRAM Discharge Volume Vent SCRAM Discharge Volume Drain SCRAM Discharge Volume Drain NA NA NA NA RHS Drain to Radwaste Outside IV 4
RHS Drain to Radwaste Inside IV 4
RHS Sample HX Inside IVs RHS Sample HX Outside IVs A,Z,F,RH A,Z,F,RH A,Z,F,RM A,Z,F,RH 30 25 NA NA NA NA c
B.
Remote Manual m
2RHS*HOV15 A,B 2RHS*HOV 1 A,B,C(o) 2RHS*HOV30 A,B 2RHS*HOV25 A,B (n) 2RHS*HOV24 A,B,C Containment Spray to Drywell Outside IV's RHS Pump Suction Outside IVs RHS Test Line to SP Outside IVs Containment Spray to Drywell Outside IVs RHS/LPCI to RPV Outside IVs 12 12 12 12 12 RH RH RM RM NA NA NA NA NA 2CSH*HOV118(n)(o) 2CSH*HOV105 2CSH*MOV107 2CSL'HOV112(o) 2CSL*MOV104 2ICS*HOV136(n)(o) 2ICS*HOV143(n)
CSH Suction from SP Outside IV 12 HPCS Hin Flow Bypass Outside IV 12 CSH to RPV Outside IV 12 CSL Suction from SP Outside IV 12 CSL to RPV Outside IV 12 ICS Suction from SP Outside IV 12 ICS Min flow to SP Outside IV 12 RH RM RM RM RM RH RH NA NA NA NA NA NA NA Amendment No.
22
TABLE 3.6.3-1 (Continued)
IMARY CONTAINMENT ISOLATION VAL~
TABLE NOTATION
- Isolates on injection signal, not primary containment isolation signal.
(a)
See Specification 3.3.2, Table 3.3.2-4, for valve groups operated by isolation signal(s).
(b)
Deleted.
(c)
These valves are the RHR heat exchangers vent lines isolation valves'he vent line connects to the RHR safety relief valves (SRVs) Discharge Header before it penetrates the primary containment.
The position indicators for these valves are provided in the Control Room for remote manual isolation.
(d)
(e)
(g)
Type C leakage tests not required.
The associated instrument lines shall not be isolated during Type A testing.
Type C testing is not required.
These valves shall be tested in accordance with Surveillance Requirement 4.6.3.4.
These valves are check valves, located on the vacuum breaker lines for RHR SRVs discharge headers.
The SRV discharge header terminates under pool water and therefore has no containment isolation valves other than those on lines feeding into it.
2SLS*MOVSA and B are globe stop check valves.
These valves close upon reverse flow.
The motor operator is provided to remote manually close the valve from the control room.
(h)
These valves are testable check valves.
They close upon reverse flow.
The air operator on each valve is provided only for periodic testing of the valve.
These valves can only be tested against a zero d/p.
Valves are maintained closed.
The FPH lines are capped.
Valves are Type C
tested.
(k)
Not primary containment penetration isolation valves.
These valves close on an isolation signal to provide integrity of "A" and "B" LPCI loops'alves close on a
SCRAM signal; not part of primary containment isolation system but are included here for Type C testing per Specification 3.6.1.2.
These valves are not required to be OPERABLE per this specification but are required to be OPERABLE per Specification 3.1.3.1.
Not subject to Type A or Type C leak test because of constant monitoring under constant 1800 psig pressure and the possible detrimental effects of shutdown.
(m)
(n)
(o)
Not subject to Type C test per
A hydrostatic test is performed in accordance with Specification 4.6 '
~ 2.d.3.
These valves are Type C tested and may be tested in the reverse direction.
Isolation barrier remains waterfi lied post-LOCA.
Isolation valve is tested with water in accordance with Specification 4.6. 1.2.i.
NINE MILE POINT UNIT 2 3/4 6-35 Amendment No. 22
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