ML17059A110
| ML17059A110 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 11/12/1993 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17059A111 | List: |
| References | |
| NUDOCS 9311300102 | |
| Download: ML17059A110 (16) | |
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+y*~4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 NIAGARA MOHAWK POWER CORPORATION DOCKET NO. 50-410 NINE MILE POINT NUCLEAR STATION UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
53 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 May 7,
- 1993, as superseded September 28,
- 1993, 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 common 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:
9311300102 931112 PDR ADDCN 05000410 P
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(2)
Tec n cal S ec'cations and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix 8, both of which are attached
- hereto, as revised through Amendment No. 53 are hereby incorporated into this license.
Niagara Nohawk 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.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 12, 1993 Rober A
- Capra, Directo Projqctg irectorate I-I Divigiph of Reactor Proje cts I/II Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT
= AMENDMENT NO.
53 TO ACILITY OPERATING LICENS NO. NPF-69 DOCKET
- 0. 50-410 Revise Appendix A as follows:
~RP X1V XXl-ll B 3/4 10-1 t
P X1V XXl-l1 3/4 10-7 (added page)
B 3/4 10-1
INDEX LIMITIN NDITI N F
R PERATION AND URVEILLAN E RE IREMENT PA E
3/4.9.10
'CONTROL ROD REMOVAL Single Control Rod Removal Multiple Control Rod Removal 3/4.9.11 RESIDUAL HEAT REMOVALAND COOLANT CIRCULATION 3/4 9-12 3/4 9-14 High Water Level Low Water Level 4.1 SPE IALTEXT EXCEPTIONS 3/4.10.1 PRIMARY CONTAINMENTINTEGRITY 3/4.10.2 ROD SEQUENCE CONTROL SYSTEM...,,
3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS..
3/4.10.4 RECIRCULATION LOOPS....
3/4.10.5 OXYGEN CONCENTRATION 3/4.10.6 TRAININGSTARTUPS....
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~ 3/49 16 3/4 9-17 3/4 10-1 3/4 10-2 3/4 10-3 3/4 10-4 3/4 10-5 3/4 10-6 3/4.10.7 INSERVICE LEAK AND HYDROSTATIC TESTING 4.11 RADIOACTIVEEFFL ENTS 3/4.11.1 LIQUID EFFLUENTS Concentration ~...
Table 4.11.1-1 Radioactive Liquid Waste Sampling and Analysis Program..
Dose Liquid Radwaste Treatment System
~
Liquid Holdup Tanks 3/4.11.2 GASEOUS EFFLUENTS Dose Rate 3/4 10-7 I
3/4 11-1 3/4 11-2'/4 11-5 3/4 11-6 3/4 11-7 3/4 11-8 NINE MILE POINT - UNIT 2 XIV Amendment No. k4 53
INDEX BA E
F R SE Tl N
.04.
4 R
F ELIN PERATI 3/4.9.1 REACTOR MODE SWITCH...
3/4.9.2 INSTRUMENTATION 3/4.9.3 CONTROL ROD POSITION...
3/4.9.4 DECAY TIME 3/4.9.5 COMMUNICATIONS 3/4.9.6 REFUELING PLATFORM 83/4 9-1 83/4 9-1 83/4 9-1 83/4 9-2 83/4 9-2 83/4 9-2 3/4.9.7 CRANE TRAVEL-SPENT FUEL STORAGE POOL........... ~... 83/4 9-2 3/4.9.8 WATER LEVEL - REACTOR VESSEL AND WATER LEVEL - SPENT 3/4.9.9 FUEL STORAGE POOL 83/4 9-2 3/4.9.10 CONTROL ROD REMOVAL 3/4.9.11 RESIDUAL HEAT REMOVALAND COOLANT CIRCULATION 3 4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIMARY CONTAINMENTINTEGRITY 3/4.10.2 ROD SEQUENCE CONTROL SYSTEM..
3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS 3/4.10.4 RECIRCULATION LOOPS 3/4.10.5 OXYGEN CONCENTRATION 3/4.10.6 TRAINING STARTUPS 3/4.10.7 INSERVICE LEAK AND HYDROSTATIC TESTING..
4.11 RADIOACTIVEEFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Concentration Dose Liquid Radwaste Treatment System....
83/4 9-2 83/4 9-3 83/4 10-1 83/4 10-1 83/4 10-1 83/4 10-1 83/4 10-1 83/4 10-1 83/4 10-1 83/4 11-1 83/4 11-1 83/4 11-2 Liquid Holdup Tanks NINE MILE POINT - UNIT 2 XX 83/4 11-2 Amendment No. g 53
I,
TABLE 1.2 OPERATI NAL NDITION NDITION 1.
Power Operation 2.
Startup 3.
Hot Shutdown 4.
Cold Shutdown 5.
Refueling tt M
DE WITCH P ITI N
Run Startup/Hot Standby Shutdown*,**
Shutdown*,** t Shutdown or Refuel* ¹ AVERAGE REACTOR OOLANTTEMPERAT RE Any temperature Any temperature 200 oF
<200'F ¹¹ 140oF TABLE N TATI N
The reactor mode switch may be placed in the Run or Startup/Hot Standby position to test the switch interlock functions provided that the control rods are verified to remain fully inserted by a second licensed operator or other technically qualified member of the unit technical staff.
The reactor mode switch may be placed in the Refuel position while a single control rod is being moved provided that the one-rod-out interlock is OPERABLE.
The reactor mode switch may be placed in the Refuel position while a single control rod drive is being removed from the reactor pressure vessel per Specification 3.9.10.1.
Fuel in the reactor vessel with the vessel head closure bolts less than fullytensioned or with the head removed.
¹ See Special Test Exceptions 3.10.1 and 3.10.3.
¹¹ See Special Test Exception 3.10.7.
NINE MILE POINT - UNIT 2 Amendment No.
53
PE IALTE T EX EPTI N
4.1
.7 IN ERVI E LEAK AND HYDR TATI TE TIN L MITIN NDITI N F
R PERATI N
3.10.7 When conducting inservice leak or hydrostatic testing, the average reactor coolant temperature specified in Table 1.2 for OPERATIONAL CONDITION 4 may be increased above 200'F, and operation considered not to be in OPERATIONAL CONDITION 3, to allow performance of an inservice leak or hydrostatic test provided the maximum reactor coolant temperature does not exceed 212'F and the following OPERATIONAL CONDITION 3 LCO's are met:
3.3.2, "Isolation Actuation Instrumentation", Functions 1.a.2, 1.b, and 3.a and b of Table 3.3.2-1; b.
3.6.5.1, "Secondary Containment Integrity";
c.
3.6.5.2, "Secondary Containment Automatic Isolation Dampers"; and d.
3.6.5.3, "Standby Gas Treatment System."
APPLICABILITY: OPERATIONAL CONDITION 4, with average reactor coolant temperature
) 200'F.
~AT~IN:
With the requirements of the above specification not satisfied, immediately enter the applicable condition of the affected specification or immediately suspend activities that could increase the average reactor coolant temperature or pressure and reduce the average reactor coolant temperature to <200'F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
RVEILLAN E RE UIREMENTS 4.10.7 Verify applicable OPERATIONAL CONDITION 3 surveillances for specifications listed in 3.10.7 are met.
NINE MILE POINT - UNIT 2 3/4 10-7 Amendment No.
53
4.1 PE IALTE T EX EPTI N
BA E
4.1
.1 PRIMARY NTAINMENTINTE RITY The requirement for PRIMARY CONTAINMENTINTEGRITY is not applicable during the period when open vessel tests are being performed during the low-power PHYSICS TESTS.
41
.2 R
D E
EN E
NTR L
Y TEM In order to perform the tests required in the Technical Specifications it is necessary to bypass the sequence restraints on control rod movement.
The additional surveillance requirements ensure that the specifications on heat generation rates and shutdown margin requirements are not exceeded during the period when these tests are being performed and that individual rod worths do not exceed the values assumed in the safety analysis.
4.1 HUTD WN MARGIN DEMONSTRATI NS Performance of shutdown margin demonstrations with the vessel head removed requires additional restrictions in order to ensure that criticality does not occur.
These additional restrictions are specified in this Limiting Condition for Operation.
4.1
.4 RECIRC LATI N LOOPS This special test exception permits reactor criticality under no-flow conditions and is required to perform certain startup and PHYSICS TESTS while at low THERMALPOWER levels.
4.10.5 OXYGEN C NCENTRATION Relief from the oxygen concentration specifications is necessary in order to provide access to the primary containment during the initial startup and testing phase of operation.
Without this access, the startup and test program could be restricted and delayed.
3 4.10.6 TRAINING STARTUPS This special test exception permits training startups to be performed with the reactor vessel depressurized at low THERMALPOWER and temperature while controlling RCS temperature with one RHR subsystem aligned in the shutdown cooling mode in order to minimize the discharge of contaminated water to the radioactive waste disposal system.
4.10.7 IN ERVI E LEAK AND HYDROSTATIC TE TIN This special test exception allows reactor vessel inservice leak and hydrostatic testing to be performed in OPERATIONAL CONDITION 4 with the maximum reactor coolant temperature not exceeding 212 F. The additionally imposed OPERATIONAL CONDITION 3 requirement for secondary containment operability provides conservatism in the response of the unit to an operational event.
This allows flexibilitysince temperatures approach 190'F during the testing and can drift higher because of decay and mechanical heat.
Additionally, because reactor vessel fluence increases over time, this testing will require coolant temperatures ) 200'F.
NINE MILE POINT - UNIT 2 8 3/4 10-1 Amendment No. k7, 53