ML17055D684
| ML17055D684 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 03/15/1988 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17055D685 | List: |
| References | |
| TAC-65889, NUDOCS 8803210460 | |
| Download: ML17055D684 (20) | |
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()Ng UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 NIAGARA MOHAWK POWER CORPORATION DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION UNIT I AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 95 License No.
DPR-63 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Niagara Mohawk Power Corporation of New York, Inc. (the licensee>
dated July 8, 1987, 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; R.
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:
8803210060 880315 PDR ADOCK 05000220 P
0
'h
(2)
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. g5
, 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 TPE NUCLEAR REGULATORY COMMISSION a,.
Robert A. Capra, Director Project Directorate I-1 Division of Reactor Projects, I/II
Attachment:
Changes to the Technical Specifications
. Date of Issuance:
q<rch 15, 19BB
t
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.
95 TO FACILITY OPERATING LICENSE NO. DPR-63 DOCKET NO. 50-220 Revise Appendix A as follows:
Remove Pa es 79 79a 80 Soa 81 81a 82 Insert Pa es 79 79a 80
'Soa 81 81a 82
1600 1400 1400 1200 800 600 (3
Cl (0
0 1000 C40 Ql Vl.~
Cl Cl p
El 0
Cl
'cal Limit For Non-Crx.t>
Operation Including Heatup/Cooldown at up to 100 F/HR 400 200 221
'100 200 300 Minimum Vessel Temperature (F)
FIGURE 3.2.2.a MINIMUMTEMPERATURE FOR PRESSURIZATION DURING HEATUP OR COOLDOWN (REACTOR NOT CRITICAL)
(HEATING OR COOLING RATE
< IOO F/HR) FOR UP TO THIRTEEN EFFECTIVE FULL POWER YEARS OF CORE OPERATION Amendment No. Q, g$ ; 95 79
44
LIMIT FOR NON-CRITICAL OPERATION INCLUDING HEAT-UP/COOLDOWN AT UP TO 100 F/H R PRESSURE
( Si
)
221 300 350 400 450 500 550 600 650 700 750 800 850 900 950 1000 1050 1100 1150 1200 1300 1400 TEMPERATURE
( F) 100 148 167 182 194 204 213 221 228 235 241 247 252 256 261 265 269 272 276 279 285 291 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 TH IRTEEN EFFECTIVE FULL POWER YEARS OF CORE OPERATION Amendment No.
$g, g$, 95 79a
II+
1600 1400 1200 800 600 400 200 U g M p
~~ o 1000 C40 tg c N.~
8 0
0 n$
n$8 Qo Limit For Power Operation (Core Critical) Including Heatup/Cooldown at up to 100 F/HR 186 945 Water Level. Must Be in Normal.
Operating Band For Core to be Critical at Temperatures (200 F
100 200 300 Minimum Vessel Temperature (F)
FIGURE 3.2.2.b MINIMUM TEMPERATURE FOR PRESSURIZATION DURING HEATUP OR COOLDOWN (REACTOR CRITICAL)
(HEATING OR COOLING RATE loO F/HR) FOR UP TO THIRTEEN EFFECTIVE FULL POWER YEARS OF CORE OPERATION Amendment No. W, P8, 95 80
ht I
LIMIT FOR POWER OPERATION (CORE CRITICAL) INCLUDING HEAT-UP/
COOLDOWN AT UP TO 100F/BR PRESSURE
( si 186 250 300 350 400 450 500 550 600 650 700 750 800 850 900 950 1000 1050 1100 1150 1200 1300 1400 TEMPERATURE F) 100 162; 188 207 222 234 244 253 261 269 275 281 287 292 296 301 305 308 312 316 319 325 331 TABLE 3 ~ 2. 2.b.
MINIMUMTEMPERATURE FOR PRESSURIZATION DURING HEAT-UP OR COOZ DOWN (REACTOR CRITICAL)
(HEATING OR COOLING RATE 100F/BR)
FOR UP TO THIRTEEN EFFECTIVE FULL POWER YEARS OF CORE OPERATION Amendment No. SP, PP, 95 80a
II'
1600 U
M Oo CJ
~ o6 O
Ig III Pg '5 Cl 0
~H t5 ClX 0
%5 1400 1200 1000 800 600 400 Limit For Znservice Test (Core Not Critical, Fuel in Vessel) 597 360 1400 200 0
0 100 130 200 300 Minimum Vessel Temperature (F)
FIGURE 3.2.2.c MINlMUM TEMPERATURE FOR PRESSURIZATION DURING HYOROSTATlC TESTlNG (REACTOR NOT CRITlCAL) FOR UP TO THIRTEEN EFFECTIVE FULL POWER YEARS OF CORE OPERATION Amendeent No. P, PP, 95
lh
LIMIT FOR IN-S ERV ICE TEST (CORE NOT CRITICALg FUEL IN VESSEL)
PRESSURE
( Si
)
360 597 700 800 900 1000 1050 1100 1150 1200 1300 1400 TEMPERATURE
( F) 100-130 130 164 186 203 216 222 228 233 237 245 253 TABLE 3. 2. 2. c MINIMUMTEMPERATURE FOR P RESSURIZATION DURING H YDROSTATIC TESTING (REACTOR NOT CRITICAL)
FOR UP TO THIRTEEN EFFECTIVE FULL PONER YEARS OF CORE OPERATION
'.i~.ndment No., p(Y, SS, 95.
81a
~
BASES FOR 3.2.2 AND 4.2.2 MINIMUM 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 100F/hr.
maximum.
(Specification 3.2.1).
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 ASME Boiler and Pressure Vessel Code 1980 Edition with Hinter 1982 Addenda.
In addition, temperature shifts due to integrated neutron flux at thirteen 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 beltline region at low and elevated temperatures and the vessel flange at intermediate temperatures.
Reactor vessel flange/reactor head flange boltup 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 beltline region.
The reactor head flange and vessel flange in combination with the double "0" ring type seal are designed to provide a leak-tight seal when bolted together.
Nhen the head is placed on the reactor vessel, only that portion of the head flange near the inside of the vessel rests on the vessel flange.
As the head bolts are replaced and tensioned, the head is flexed slightly to bring together the entire contact surfaces adjacent to the "0" rings of the head and vessel flanges.
Both the head and vessel flanges have a
NDT temperature of 40F and they are not subject to any appreciable neutron radiation exposure.
Therefore, the minimum vessel flange and head flange temperature for bolting 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 shift 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 installed inside the vessel.
The curves are applicable for up to thirteen 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 ASTM E185-66 except for the material withdrawal schedule which is specified in Specification 4.2.2.b.
Amendment No. 4f, 05,
'95 82
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