ML17055B794
| ML17055B794 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 06/10/1986 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17055B797 | List: |
| References | |
| TAC-65889, NUDOCS 8606130347 | |
| Download: ML17055B794 (24) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 NIAGARA MOHAWK POWER CORPORATION DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
85 License No.
DPR-63 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Niagara Mohawk Power Corporation (the licensee) dated January 28, 1986, 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 I; 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.
DPR-63 is hereby amended to read as follows:
8606f30347 860610 PDR ADOCK 05000220 P
PDR.
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(2) Technical S ecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.
B5
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR T N CLEAR REGUL OR OMMISSION Joh A. Zwolinski, Director BMR Project Directorate 81 Divssion of BMR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 3.O, 1996
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ATTACHMENT TO LICENSE AMENDMENT NO.
FACILITY OPERATING LICENSE NO.
DPR-63 DOCKET NO. 50-220 Revise the identified identified indicating Appendix A Technical Specifications by removing the pages below and inserting the attached pages.
The revised pages are by the captioned amendment number and contain marginal lines the area of change.
REMOVE 77 78 79 79a 80 80a 81 Sla 82 82a 82b INSERT 77 78 79 79a 80 Soa 81 Sla 82
LIHITING CONDITION FOR OPERATION SURVEILLANCE RE IREHENT 3.2.2 HINIHUH REACTOR VESSEL TEHPERATURE FOR PRESSURIZATION bJJ11 bttttg Applies to the minimum vessel temperature required for vessel pressurization.
O~b ective:
To assure that no substantial pressure is imposed on the reactor vessel unless its temperature is considerably above.its Nil Ductility Transition Temperature (NDTT).
b~Mt t a.
During reactor vessel heatup and cooldown when the reactor is not critical, the reactor vessel temperature and pressure shall satisfy the requirements of Figure 3.2.2.a.
b.
During reactor vessel heatup and cooldown when the reactor is critical, the reactor vessel temperature and pressure shall satisfy the requirements of Figure 3.2.2.b.
except when performing low power physics testing with the vessel head removed at power levels not to exceed 5 mw(t).
4.2.2 HINIHUH REACTOR VESSEL TEHPERATURE FOR P RE SSURI ZATION bi tt Applies to the required vessel temperature for pressurization.
O~becti ve:
To assure that the vessel is eot sub]ected to any substantial pressure unless its temperature is greater than its Nil Ductility Transition Temperature (NDTT).
- a. Reactor vessel temperature and pressure shall be monitored and controlled to assure that the pressure and temperature limits are met.
- b. Vessel material and surveillance samples located within the core region to permit periodic monitoring of exposure and material properties shall be inspected on the following schedule:
First capsule - one fourth service life Second capsule - three fourth service life Third capsule standby In the event the surveillance specimens at one quarter of the vessels service life indicate a shift of reference temperature greater than predicted the schedule shall be revised as follows:
Amendment Wo. Q, Second capsule one half service life Third capsule standby 77
LIHITING CONDITION FOR OPERATION SURVEILLANCE REQUIREHENT c.
During hydrostatic testing, the reactor vessel temperature and pressure shall satisfy the requirements of Figure 3.2.2.c. if the core is not critical.
d.
The reactor vessel head bolting studs shall not be under tension unless the temperature of the vessel head flange and the head are equal to or greater than 100F.
Amendment No. 58, 85 78
1600 1400 1400 1200 600 400 8
Cll 0 1000 0
4 g Ee g 800 0
IE Q g g0l X
'cal Limit For Non-Crate Operation Including Heatup/Cooldown at up to 100 F/HR 200 236 100 200
.Minimum Vessel Temperature (F) 300 FIGURE 3.2.2.a MINIMUMTEMPERATURE FOR PRESSURIZATION DURING HEATUP OR COOLDOWN (REACTOR NOT CRITICAL)
(HEATING OR COOLING RATE + l00 F/HR) FOR UP TO ELEVEN EFFECTIVE FULL POWER YEARS OF CORE OPERATION I
79 Amendment No. 55,85
LIMIT'OR NON-CRITICAL OPERATION INCLUDING HEAT-UP/COOLDOWN AT UP TO'00F/HR 236 300 350 400 450 500 550 600 650 700 750 800 850.
900 950 1000 1050 1100 1150 1200 1300 1400 TEMPERATURE F
100 135 154.
170 182 192 201 209 217 223 229 234 240 244 248 253 256 260 263 267 273 279 TABLE 3.2. 2. a MINIMUM TEMPERATURE FOR PRESSURIZATION DURING HEAT-UP OR COOLDOWN (REACTOR NOT CRITICAL)
(HEATING OR COOLING RATE 100F/HR)
FOR UP TO ELEVEN EFFECTIVE FULL POSER YEARS OF CORE OPERATION Amendment Wo. Q,85 79a
1600 1400 1200 1105 U gp0 1000 C4 4 ~
< c 07 ~
I
- n. ~
4 0
04 Cl op 0
t5 Limit For Power Operation (Core Critical) Including Heatup/Cooldown. at up to 100 F/HR 800 400 Water Level Must Be in Normal Operating Band For Core to be Critical at Temoeratures c200 F
200 194 100 200 Minimum Vessel Temperature (F) 300 Amendment No.
$8 85 FIGURE 3.2.2.b MINIMUM TEMPERATURE FOR PRESSURIZATION DURING HEATVP OR COOLDOWN {REACTOR CRITICAL)
%EATING OR COOLING RATE l00 F/HR) FOR UP TO ELEVEN EFFECTiVE FULL POWER YEARS OF CORE OPERAT'lON i
LIMIT FOR POWER OPERATION (CORE CRZTZCAL) INCLUDING HEAT-UP/
COOLDOWN AT UP TO 100F/BR P RESSURE si 194 250 300 350 400 450 500 550 600 650 700 750 800 850 900 950 1000 1050 1100 1150 1200 1300 1400 TEMPE RATURE 100 150 176 194 210 222 232 241 249 257 263 269 274 280 284 288 293 296 300 303 307 313 319 TABLE 3.2.2. b MINIMUMTEMPERATURE FOR PRESSURIZATION DURING HEAT-UP OR COOLDOWN (REACTOR CRITICAL)
(HEATING OR COOLING RATE 100F/BR)
FOR UP TO ELEVEN EFFECTIVE FULL POWER YEARS OF CORE OPERATION Amendment No.
SS, 85 soa
1600 1400 1200 Limit For Inservice Test (Core Not Critical, Fuel in Vessel}
l400 1000 800 600 628 400 360 200 I
100 130 200 Minimum Vessel Temperature (F) 300 FlGURE 3.2.2.c MINIMUM TEMPERATURE FOR PRESSURIZATlON DURING HYDROSTATIC TESTlNG (REACTOR NOT CRITICAL) FOR UP TO ELEVEN EFFECTIVE FULL POWER YEARS OF CORE OPERATION 81 Amendment No. Sg,85
LIMIT FOR IN-SERVICE TEST (CORE NOT CRITICALg FUEL IN VESSEL)
PRESSURE
( si
)
360 628 700 800 900 1000 1050 lloo 1150 1200 1300 1400 TEMPERATURE
( F) 100-130 130 152 174 190 204 210 215 220 225 233 241 TABLE 3 ~ 2 ~ 2 c MINIMUM TEMPERATURE FOR PRESSURIZATION DURING 8 YDROSTATIC TESTING (REACTOR NOT CRITICAL)
FOR UP TO ELEVEN EFFECTIVE FULL PONER YEARS OF CORE OPERATION Amendment No.
$8,85 8la
BASES FOR 3.2.2 AND '4.2.2 HINIHUH REACTOR VESSEL TEMPERATURE FOR PRESSURIZATION Figures 3.2.2.a and 3.2.2.b are plots of pressure versus temperature for a heat-up and cool down rate of )OOF/hr.
maximum.
(Specification 3.2.)).
Figure 3.2.2.c is a plot of pressure versus temperature for hydrostatic testing.
These curves are based on calculations of stress intensity factors according to Appendix G of Section III of the ASHE Boiler a'nd Pressure Vessel Code 1980 Edition with Winter )982 Addenda.
In addition, temperature shifts due to integrated neutron flux at eleven effective full power years of operation were incorporated into the figures.
These shifts were calculated from the formula presented in Regulatory Guide 1.99, proposed Revision 2.
These curves are applicable to the belt)inc region at low and elevated temperatur es and the vessel flange at intermediate temperatures.
Reactor vessel flange/reactor head flange bo)tup is governed by other criteria as stated in Specification 3.2.2.d.
The pressure readings on the figures have been adjusted to reflect the calculated elevation head difference between the pressure sensing instrument locations and the pressure sensitive area of the core belt)inc region.
The reactor vessel head flange and vessel flange in'combination with the double "0" ring type sea) are designed to provide a leak-tight seal when bolted together.
When the vessel head is placed on the reactor vessel, only that portion of the head flange near the inside of the vessel rests on the vessel f)ange.
As the head bo)ts are replaced and tensioned, the vessel head is flexed'lightly to bring together the entire contact surfaces adjacent to the "0" rings of the head and vessel f)ange.
Both the head and vessel and f)ange have a
HDT temperature of 40F and they are not subject to any appreciable neutron radiation exposure.
Therefore, the minimum vessel head and head flange temperature for bolting the head flange and vessel flange is established as 40 + 60F. or 100F.
Figures 3.2.2.a.
3.2.2.b.
and 3.2.2.c.
have incorporated a temperature sh>ft due to the calculated integrated neutron flux.
The integrated neutron flux at the vessel wall is calculated from core physics data and has been measured using flux monitors insta))ed inside the vessel.
The curves are applicable for up to eleven effective full power years of operation.
Vessel material surveillance samples are located within the core region to permit periodic monitoring of exposure and material properties relative to control samples.
The material sample program conforms with ASTH E)85-66 except for the material withdrawal. schedule which is specified in Specification 4.2.2.b.
Amendment Ho.
$8, 85 82