ML17056B247
| ML17056B247 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 01/11/1991 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17056B248 | List: |
| References | |
| NUDOCS 9101230219 | |
| Download: ML17056B247 (38) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 NIAGARA MOHAMK POMER CORPORATION DOCKET NO. 50-410 NINE MILE POINT NUCLEAR STATION UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 26 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 March 21,
- 1990, as amended November 13, 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 wi11 operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
D.
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; 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 2.
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.
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:
910i2302i9 9i0iiil~
PDR ADOCK 050004iO p
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(2)
Technical S ecifications 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. 26 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 Robert A. Capra, Director Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Date of Issuance:
January 11, 1991
I
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.. TO FACILITY OPERATING, LICENSE NO.
NPF-69 DOCKET NO. 50-410 Revise Appendix A as follows:
Remove Pa e
X 3/4 4-24 3/4 4-25 3/4 4-26 3/4 4-27 3/4 4-28 3/4 4-29 3/4 4-30 3/4 4-31 3/4 4-32 3/4 4-33 3/4 4-34 W W B 3/4 4-5 B 3/4 4-6 Insert Pa e
X 3/4 4-24 3/4 4-25 3/4 4-26 3/4 4-27 3/4 4<<28 3/4 4-29 3/4 4-30 3/4 4-31 3/4 4-32 3/4 4-33 3/4 4-34 3/4 4-35 3/4 4-36 B 3/4 4-5 B 3/4 4-6
0
INDEX REACTOR COOLANT SYSTEM (Continued) 3/4.4.6 PRESSURE/TEMPERATURE LIMITS Reactor Coolant System.....'........
PAGE 3/4 4-24 Figure 3.4.6.1-1 Minimum Beltline Downcomer Hater Temperature for Pressurization During In-Service Hydrostatic Testing and Leak Testing (Reactor Not Critical)...... 3/4 4-26 Figure 3.4.6.1-2 Minimum Beltline Downcomer Hater Temperature for Pressurization During Heatup and Low-Power Physics Tests (Reactor Not Critical) (Heating Rate 100 F/HR)..
3/4 4-27 Figure 3.4.6.1-3 Minimum Beltline Downcomer Hater Temperature for Pressurization During Cooldown and Low-Power Physics Tests (Reactor Not Critical) (Cooling Rate 100 F/HR)...
3/4 4-28 Figure 3.4.6.1-4 Minimum Beltline Downcomer Water Temperature for Pressurization During Core Operation (Core Critical) (Heatup at a "Heating Rate 100 F/HR)......
3/4 4-29 Figure 3.4.6.1-5 Minimum Beltline Downcomer Water Temperature for Pressurization During Core Operation (Core
'ritical) (Cooldown at a Cooling Rate
< 100 F/HR).... 3/4 4-30 3/4.4.7 3/4.,4.8 3/4.4.9 MAIN STEAM LINE ISOLATION VALVES STRUCTURAL INTEGRITY.
RESIDUAL HEAT REMOVAL Hot Shutdown.......
Cold Shutdown...
Table 4.4.6.1.3-1 Reactor Vessel Material Surveillance Program Withdrawal Schedule..
Reactor Steam Dome 3/4 4-31 3/4 4-32 3/4 4-33 3/4 4-34 3/4 4-35 3/4 4-36 3/4.5 3/4.5
~ 1 3/4.5.2 3/4.5.3 3/4.6 3/4.6.1 EMERGENCY CORE COOLING SYSTEMS ECCS OPERATING...............
ECCS SHUTDOWN.
SUPPRESSION POOL...
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT Primary Containment Integrity....
Primary Containment Leakage 3I4 5-1
~
. 3/4 5-7 3/4 5-9 3/4 6-1
. 3/4 6-2 NINE MILE POINT UNIT 2 Amendment No.
26
REACTOR COOLANT SYSTEM 3/4.4.6 PRESSURE/TEMPERATURE LIMITS REACTOR COOLANT SYSTEM 3.4.6.1 The reactor coolant system temperature and pressure shall be limited in accordance with the limit lines shown on Figure 3.4.6.1-1 for hydrostatic or leak testing; Figure 3.4.6.1-2 for heatup by non-nuclear
- means, Figure 3.4.6.1-3 for cooldown following a nuclear shutdown and low-power PHYSICS TESTS; and Figures 3.4.6.1-4 and 3.4.6.1-5 for operations with a critical core other than low-power PHYSICS TESTS, with:
a.
A maximum heatup of 100'F in any 1-hour period, b.
A maximum cooldown of 100'F in any 1-hour period, c.
A maximum temperature change of less than or equal to 20'F in any 1-hour period during inservice hydrostatic and leak testing operations above the heatup and cooldown limit curves, and d.
The reactor vessel flange and head flange temperature greater than or equal to 70'F when reactor vessel head bolting studs are under tension.
APPLICABILITY:
At all times.
ACTION:
With any of the above 1-imits exceeded, restore the temperature and/or pressure to within the limits within 30 minutes; perform an engineering evaluation to determine the effects of the out-of-limit condition on the structural integrity of the reactor coolant system; determine that the reactor coolant system remains a'cceptable for continued operations, or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOHN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4.4.6.1.1 During system heatup,
- cooldown, and inservice leak and hydrostatic testing operations, the reactor coolant system temperature and pressure shall be determined to be within the above required heatup and cooldown limits and to the right of the limit lines of Figures 3.4.6.1-1, 3.4.6.1-2, 3.4.6.1-3, 3.4.6.1-4, and 3.4.6.1-5 as applicable, at least once per 30 minutes.
NINE MILE POINT UNIT 2 Amendment No. 26 3/4 4-24
REACTOR COOLANT SYSTEM PRESSURE TEMPERATURE LIMITS 4.4.6.1.2 The reactor coolant system temperature and pressure shall be determined to be to the right of the criticality limit line of Figures 3.4.6.1-4 and 3.4.6.1-5 within 15 minutes before the withdrawal of control rods to bring the reactor to criticality and at least once per 30 minutes during system heatup.
Provided the water level is in the range for power operation, the core may be critical when left of the criticality limit line if the pressure is maintained below 312 psig (see cross-hatched region in Figures 3.4.6.1-4 and 3.4.6;1-5).
In this case, the reactor coolant temperature and pressure shall be determined to be within the cross-hatched region of figures 3.4.6.1-4 and 3.4.6.1-5 within 15 minutes before withdrawal of control rods to bring the r'eactor to criticality and at least once per 30 minutes during system heatup.
4.4.6.1.3 The reactor vessel material surveillance specimens shall be removed and examined to determine changes in reactor pressure vessel material properties as required by 10CFR50, Appendix H, in accordance with the schedule in Table 4.4.6.1.3-1.
The results of these examinations shall be used to bring up to date the curves of Figures 3.4.6.1-1, 3.4.6.1-2, 3.4.6.1-3, 3.4.6.1-4 and 3.4.6.1-5.
4.4.6.1.4 The reactor vessel flange and head flange temperature shall be verified to be greater than or equal to 70'F when reactor vessel head bolting studs are under full tension:
a.
In OPERATIONAL CONDITION 4 when reactor coolant system temperature is:
1.
<90'F, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
2.
<80 F, at least once per 30 minutes.
b.
Nithin 30 minutes before, and at, least once per 30 minutes during, tensioning of the reactor vessel head bolting studs.
NINE MILE POINT UNIT 2 Amendment No.
26 3/4 4-25
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NINE MILE POINT UNIT 2
HEATUP CORE NOT CRITICAl
, '1400 5 200
~w Q m O
~ 0 N'dOl CC CL CC C' LP cC ut aQ g 1000 800 600 417 400 312 200 NON-CRITICAL HEATUP MINIMA!
TElvPERATLRE FOR BOLTS 70 F 0
70 130 0
50 100 150 200 250 300 350 DOWNCOMER WATER TEMPERATUREtp)
FIGURE 3.4.6.1-2 MINIMUM BELTLINE DOWNCOMER WATER TEMPERATURE FOR, PRESSURIZATION DURING HEATUP AND LOW-POWER PHYSICS TESTS (REACTOR NOT CRITICAL)
(HEATING RATE 5 100 F/HR)
FOR UP TO 12 '
EFFECTIVE FULL POWER YEARS OF OPERATION NINE MILE POINT - UNIT 2 Amendment No. 26 3/4 4-27
I
NINE MILE POINT UNIT 2 COOLOOVrN CORE NOT CRITICAL
,. 1400 1200 312 200 l
4o+
1000 Ch L
800
~
600 sea O N 400 QJ NON-CRITICAL COOLDOWN MINltvLM TElvPERATLRE FOR BOLTLP 70 F 0
70, 130 0
So 100 1SO 200 ZSO Ooo SSa DOWNCOMER WATER TEMPERATUREtF)
FIGURE 3.4.6.1-3 MINIMUM BELTLZNE DOWNCOMER WATER TEMPERATURE FOR PRESSURIZATION DURING COOLDOWN AND LOW-POWER PHYSICS TESTS (REACTOR NOT CRITICAL)
(COOLING RATE < 100 F/HR)
FOR UP TO 12 '
EFFECTIVE FULL POWER YEARS OF OPERATION NINE MILE POINT - UNIT 2 Amendment No.
26 3/4 4-28
NINE MILE POINT UNIT 2 CORE OPERATlON {HEATUP)
C5
~ ck QJ lA g
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Ch ac L, m O
~a lC O 0 I
Vl aik g 1400 5 200 1000 800 600 517 400 312 200 WATER LEVEL hUST BE N RANGE FCA POWER ~TICN IF CCRE IS CRITICAL BELOW
~W F CORE HEATUP OPERATlON MINIMAL TEMPERATLRE FCR BOLTLP 70 F 70 197 0
50
'100
'150 200 250 SOQ S50 DOWNCOMER WATER TEMPERATURE{F)
FIGURE 3.4.6.1-4 MINIMUM BELTLINE DOWNCOMER WATER TEMPERATURE FOR PRESSURIZATION DURING CORE OPERATION (CORE CRITICAL)
(HEATUP AT A HEATING RATE 100 F/HR)
FOR UP TO 12 '
EFFECTIVE FULL POWER YEARS OF OPERATION NINE MILE POINT UNIT 2 Amendment No.
26 3/4 4-29
NINE MILE POINT UNIT 2 CORE OPERATION (COOLDOWN) 1400 1 200 a
$ 000 SO0 C/l gg 400 312 ZOO WATER LEVH ~T BE N RANGE FOR DOWER ODERATION IF CCRE IS CRITICAI BEI OW 166 F, CORE COOLING OPERATION MINlh4JA TElvPERA TLUTE FOFl BOLTLP 70 F 70 104 166 0
SO 100 150 200 250 300 350 DOWN C4MER WATER TEMPERATURE(F)
FIGURE 3.4.6.1-5 MINIMUM BELTLINE DOWNCOMER WATER TEMPERATURE FOR PRESSURIZATION DURING CORE OPERATION (CORE CRITICAL)
(COOLDOWN AT A COOLING RATE ~ 100 F/HR)
FOR UP TO 12.8 EFFECTIVE FULL POWER YEARS OF OPERATION NINE MILE POINT - UNIT 2 Amendment No. 26 3/4 4-30
TABLE 4. 4. 6. l. 3-1 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM - WITHDRAWAL SCHEDULE CAPSULE NUMBER VESSEL LOCATION 30 183o LEAD FACTOR 9 1/4 T 0.41 41
- 0. 41 WITHDRAWAL TIME EFPY 10'0 Spare NINE MILE POINT - UNIT 2 Amendment No.
26 3/4 4-31
l HeV). As a result, the nozzles are predicted to have an EOL RTNDT of -13'F and the limiting weld material will have an EOL RTNDT of -12 F. Hect 45 ft-lb and 25 mils lateral expansion requirement at 10 F. E I