ML17059C380

Amend 164 to License DPR-63,changing TS 3.2.2, Minimum Reactor Vessel Temp for Pressurization, & Associated TS Bases to Update P/T Operating Curves & Tables for Continued Plant Operation Up to 28 Effective full-power Years

ML17059C380
Person / Time
Site:	Nine Mile Point
Issue date:	11/25/1998
From:	Bajwa S NRC (Affiliation Not Assigned)
To:
Shared Package
ML17059C381	List: ML17059C380 ML17059C382
References
DRP-63-A-164, NUDOCS 9812080181
Download: ML17059C380 (38)

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.c. 20555-0001 NIAGARAMOHAWKPOWER CORPORATION DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION UNIT 1 AMENDMENTTO FACILITYOPERATING LICENSE Amendment No.

164 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 June 19, 1998, as supplemented by letter dated November 6, 1998, 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 facilitywilloperate 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 willbe conducted in compliance with the Commission's regulations; D. The issuance of this amendment willnot 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:

9812080i8i 98if25 PDR ADGCK 05000220 P

PDR

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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 B, both of which are attached hereto, as revised through Amendment No. 1 64 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 before core operation exceeds 18 effective full-poweryears.

Attachment:

Changes to the Technical Specifications S. Singh Bajwa, Director Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Date of Issuance:

November 25, 1998

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ATTACHMENTTO LICENSE AMENDMENTNO.

TO FACILITYOPERATING LICENSE NO. DPR-63 DOCKET NO. 50-220 Replace the following page of the Appendix A Technical Specifications with the attached page.

Remove 84 85 86 87 88 89 90 91 92 93 94 95 Insert 84 85 86 87 88 89 90 91 92 93 94 94a (new) 94b (new) 94c (new) 94d (new) 95

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LIMITINGCONDITION FOR OPERATION SURVEILLANCEREQUIREMENT C.

d.

During leakage and hydrostatic testing, the reactor vessel temperature and pressure shall satisfy the requirements of Figures 3.2.2.e, 3.2.2.f, or 3.2.2.g, as appropriate, if the core is not critical. During reactor vessel heatup and cooldown for the purpose of leakage and hydrostatic testing, the reactor vessel temperature and pressure shall satisfy the requirements of Figures 3.2.2.a and 3.2.2.b for non-critical heatup and cooldown, respectively.

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 100'F.

In order to generate additional plant-specific data, a capsule containing irradiated and unirradiated material will be re-inserted at the B capsule location.

Re-insertion capsules have already been installed at the A and C locations.

A prime (') is used to ihdicate a re-insertion capsule.

The withdrawal schedule for the re-insertion capsules is as follows:

Fourth capsule (A') - 24 EFPY

. Fifth capsule (C') - 32 EFPY Sixth capsule (B') - 40 EFPY AMENDMENTNO. Ilk 164 84

HEATUP - CORE NOT CRITICAL 1500 1000 REACTOR PRESSURE (psig) 500 0

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I Minimum Temperature for Boltup:

100 F 0

50 100 150 200 250 300 350 400 REACTOR VESSEL BELTLINE DOWNCOMER WATER TEMPERATURE (F)

(reactor vessel beltline downcomer voter temperature is measured at recirculation loop suction)

(instrument uncertainties have been included in this figure)

MINIMUMBELTLINEDOWNCOMERWATERTEMPERATURE FOR PRESSURIZATION DURING HEATUP ANDLOW-POWER PHYSICS TESTS (CORE NOT CRITICAL)(HEATINGRATE z 100'F/HR)

FOR UP TO 28 EFFECTIVE FULLPOWER YEARS OF OPERATION ANENDMENT NO. Egg 164 85

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LIMITFOR NON-CRITICALOPERATION HEATUP ATUP TO 100'F/HR 197 197 197 197 199 205 213 225 239 257 279 304 334 369 410 458 513 577.

651 737 835 949 1079 100 110 120 130 140

'50 160 170 180 190 200 210 220 230 240 250 260 270 280 290 300 310 320 (reactor vessel beltline downcomer water temperature is measured at recirculation loop suction)

(instrument uncertainties have been included in this table)

TABLE3.2.2.a MINIMUMTEMPERATURE FOR PRESSURIZATION DURING HEAT-UP (CORE NOT CRITICAL)(HEATINGRATE s 100'F/HR)

FOR UP TO TWENTYEIGHT EFFECTIVE FULLPOWER YEARS OF CORE OPERATION AMENDMENT NO Egg 1 64 86

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COOLDOWN - CORE NOT CRITICAL 1500 1000 REACTOR PRESSURE (PSI9) 500 0

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Minimum Temperature for Boltup:

100 F 0

50 100 150 200 250 300 350

'400 REACTOR VESSEL BELTLINE DOWNCOMER WATER TEMPERATURE (F)

(reactor vessel beltline downcomer water temperature is measured at recirculation loop suction)

(instrument uncertainties have been included in this figure)

FIGURE 322.b MINIMUIVIBELTLINEDOWNCOMER WATERTEMPERATURE FOR PRESSURIZATION DUIUNGCOOLDOWN ANDLOW-POWER PHYSICS TESTS (CORE NOT CRITICAL)(COOLING RATE s 100'F/HR)

FOR UP TO 28 EFFECTIVE FULLPOWER YEARS OF OPERATION AMENDMENT NO. ling 164 S7

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LIMITFOR NON-CRITICALOPERATION COOLDOWNATUP TO 100'F/HR 160 171 184 199 216 235 258 284

'15 350 391 438 493 556 630 708 786

" 866 957 1062 100 110 120 130 140 150 160 170 180 190 200 210 220 230 240 250 260 270 280 290 (reactor vessel beltline downcomer water temperature is measured at recirculation loop suction)

(instrument uncertainties have been included in this table)

TABLE3.2.2.b MINIMUMTEMPERATURE FOR PRESSURIZATION DURING COOLDOWN (CORE NOT CRITICAL)(COOLING RATE s 100'F/HR)

FOR UP TO TWENTYEIGHT EFFECTIVE FULLPOWER YEARS OF CORE OPERATION AMENDNENT NO. Zgg 164

HEATUP - CORE CRITICAL 1500

. 1000 REACTOR PRESSURE (psig) 500 0

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Minimum Temperature for Boltup:

100 F gg Water Level Must Be in Range For Power Operation IfCore Is Cnticai Below 278 F 0

50 100 150 200 250 300 350 400 REACTOR VESSEL BELTLINE DOWNCOMER WATERTEMPERATURE (F)

(reactor vessel beltline downcomer water temperature is measured at recirculation loop suction)

(instrument uncertainties have been included in this figure)

FIGURE 322.c MINIMUMBELTLINEDOWNCOMERWATERTEMPERATURE FOR PRESSURIZATION DURING CORE OPERATION (CORE CRITICAL)(HEATINGRATE s 100'F/HR) FOR UP TO 28 EFFECTIVE FULLPOWER YEARS OF OPERATION AMENDMENT NO. Egg 164 89

LIMITFOR POWER OPERATION (CORE CRITICAL)

HEATUP ATUP TO 100'F/HR 197 197 197 197 197 197 197 197 199 205 213 225 239 257 279 304 334 360 360 360 402 410 458 513 577 65) 737 835 949 1079 100 110 120 130 140 150 160 170 180 190 200

," 210 220 230 240 250 260 268 270 277 278'80 290 300 310 320 330 340 350 360 (reactor vessel beltline downcomer water temperature is measured at recirculation loop suction)

('water level must be in range for power operation ifcore is critical below 278 F)

(instrument uncertainties have been included in this table)

TABLE3.2.2.c MINIMUMTEMPERATUI&FOR PRESSURIZATION DURING

. HEATUP (CORE CRITICAL)(HEATINGRATE s 100'F/HR)

FOR UP TO TWENTYEIGHT EFFECTIVE FULLPOWER YEARS OF CORE OPERATION AMENDMENT NO. Egg 164 90

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COOLDOWN - CORE CRITICAL 1500 1000 REACTOR PRESSURE (psig) 500 0

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I Ir Minimum Temperature for Boltup:

100 F Q Water Level Must Be in Range For Power Operation IfCore Is Critical Below 260 F 0

50 100 150 200 250 300 350

'400 REACTOR VESSEL BELTLINE DOWNCOMER WATER TEMPERATURE (F)

(reactor vessel beltline downcomer water temperature is measured at recirculation loop suction)

(instrument uncertainties have been included in this figure)

FIGURE 322.d MINIMUMBELTLINEDOWNCOMER WATERTEMPERATURE FOR PRESSURIZATION DURING CORE OPERATION (CORE CRITICAL)(COOLING RATE s100'F/HR) FOR UP TO 28 EFFECTIVE FULLPOWER YEARS OF OPERATION ANENDMENT NO-7gg 164 91

LIMITFOR POWER OPERATION (CORE CRITICAL)

COOLDOWNATUP TO 100'F/HR 130 136 143 151 160 171 184 199 216 235 258 284 315 350 360 360 360 360 493 556 630 708 786 866 957

.1062 100 110 120 130 140 150 160 170 180 190 200 210 220 230 233 240 250 259 260'70 280 290 300 310 320 330 (reactor vessel beltline downcomer water temperature is measured at recirculation loop suction)

('water level must be in range for power operation ifcore is critical below 260 F)

(instrument uncertainties have been included in this table)

TABLE3.2.2.d MINIMUMTEMPERATURE FOR PRESSURIZATION DUIGNG COOLDOWN (CORE CRITICAL)(COOLING RATE s 100'F/HR)

FOR UP TO TWENTYEIGHT EFFECTIVE FULLPOWER YEARS OF CORE OPERATION AMENDNENT NO. Egg 164 92

1'g

LEAK/HYDROTEST - CORE NOT CRITICAL 1500 1000 REACTOR PRESSURE (psig) 500 0

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Minimum Temperature for Boltup:

100 F 0.

50 100 150 200 250 300 350 400 REACTOR VESSEL BELTLINE DOWNCOMER WATER TEMPERATURE (F)

(reactor vessel beltline downcomer water temperature is measured at recirculation loop suction)

(instrument uncertainties have been included in this figure)

FIGURE 322.e MINIMUMBELTLINEDOWNCOMERWATERTEMPERATURE FOR PRESSURIZATION DUMNGIN-SERVICE HYDROSTATIC TESTING'ND LEAKTESTING (CORE NOT CRITICAL)FOR UP TO 28 EFFECTIVE FULLPOWER YEARS OF OPERATION ANEHDMENT NO. Zgg 164 93

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LIMITFOR IN-SERVICE TEST (CORE NOT CRITICAL,FUEL IN VESSEL) 360 360 360 360 569 590 614 642 675 712 755 S05 862 929 1005 1032 1093 1195 100 110 120 130 140 150 160 170 1SO 190 200 210 220 230 240 243 250 260 (reactor vessel beltline downcomer water temperature is measured at recirculation loop suction)

(instrument uncertainties have been included in this table)

TABLE3.2.2.e MINIMUMTEMPERATURE FOR PRESSURIZATION DURING LEAK/HYDROSTATICTESTING (CORE NOT CRITICAL)

FOR UP TO TWENTYEIGHT EFFECTIVE FULLPOWER YEARS OF CORE OPERATION AMENDMENT NO. H2 164

LEAK/HYDROTEST - CORE NOT CRITICAL 1500 1000 REACTOR PRESSURE (P~iQ) 500 0

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Minimum Temperature for Boltup:

100 F 0

50

. 100.

150 200 250 300 350 400 REACTOR VESSEL BELTLINE DOWNCOMER WATERTEMPERATURE (F)

(reactor vessel beltline downcomer water temperature is measured at recirculation loop suction)

(instrument uncertainties have been included in this figure)

FIGURE 322.f MINIMUMBELTLINEDOWNCOMER WATERTEMPERATURE FOR PRESSURIZATION DURING IN-SERVICE HYDROSTATICTESTING ANDLEAKTESTING (CORE NOT CRITICAL)FOR UP TO 20 EFFECTIVE FULLPOWER YEARS OF OPERATION AMENDMEN'f NO.

1 64 94a

LIMITFOR IN-SERVICE TEST (CORE NOT CRITIC'AL,FUEL INVESSEL) 360 360 360 360 597 622 652 685 724 769 821

'81 951 1031 1123 1229 100 110 120 130 140 150 160 170 180 190 200 210 220 230 240 250 (reactor vessel beltline downcomer water temperature is measured at recirculation loop suction)

(instrument uncertainties have been included in this table)

TABLE3.2.2.f MINIMUMTEMPERATURE FOR PRESSURIZATION DURING LEAK/HYDROSTATICTESTING (CORE NOT CRITICAL)

FOR UP TO TWENTYEFFECTIVE FULLPOWER YEARS OF CORE OPERATION AMENDMENT NO.

1 64 94b

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LEAK/HYDROTEST

-. CORE NOT CRITlCAL 1500 1000 REACTOR PRESSURE (prig) 500 0

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I Minimum Temperature for Boltup:

100 F 0

50 100 150 200 250 300 350 400 REACTOR VESSEL BELTLINE DOWNCOMER WATER TEMPERATURE (F)

(reactor vessel beltline downcomer water temperature is measured at recirculation loop suction)

(instrument uncertainties have been included in this figure)

FIGURE 3.2.2.g MINIMUMBELTLINEDOWNCOMER WATERTEMPERATURE FOR PRESSURIZATION DUIGNG IN-SERVICE HYDROSTATICTESTING ANDLEAKTESTING (CORE NOT CRITICAL)FOR UP TO 24 EFFECTIVE FULLPOWER YEARS OF OPERATION AMENDMENT NO.

1 64

p' LIMITFOR IN-SERVICE TEST (CORE NOT CRITICAL,FUEL INVESSEL) 360 360 360 360 582 604 631 661 697 737 785 839 902 974 1033 1058 1154.

100 110 120 130 140 150 160 170 180 190 200 210 220 230 237 240 250 (reactor vessel beltline downcomer water temperature is measured at recirculation loop suction)

(instrument uncertainties have'been included in this table)

TABLE3.2.2.g MINIMUMTEMPERATURE FOR PRESSURIZATION DURING LEAIGHYDROSTATICTESTING (CORE NOT CRITICAL)

FOR UP TO TWENTYFOUR EFFECTIVE FULLPOWER YEARS OF CORE OPERATION AMENDMENT NO.

1 64

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BASES FOR 3.2.2 AND4.2.2 MINIMUMREACTOR VESSEL TEMPERATURE FOR PRESSURIZATION Figures 3.2.2.a, 3.2.2.b, 3.2.2.c, and 3.2.2.d are plots of pressure versus temperature for heatup and cooldown rates of up to 100'F/hr.

maximum (Specification 3.2.1).

Figures 3.2.2.e, 3.2.2.f, and 3.2.2.g are plots of pressure versus temperature for leakage and hydrostatic testing.

When the minimum temperature for leakage and hydrostatic testing is reached, a thermal soak shall be performed to ensure that the thermal gradient across the vessel wall is negligible.-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 Winter 1982 Addenda.

In addition, temperature shifts due to fast neutron fluence at twenty-eight effective full power years of operation were incorporated into the figures.

These shifts were calculated using the procedure presented in Regulatory Guide 1.99, Revision 2. 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 account for instrument uncertainties and to reflect the calculated elevation head difference between the pressure sensing instrument locations and the pressure sensitive area of the core beltline region.

The temperature readings on the figures have been adjusted to account for instrument uncertainties.

The reactor vessel 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.

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 flange.

As the head bolts are replaced and tensioned, the vessel 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 an NDT temperature of 40'F and they are not subject to any appreciable neutron radiation exposure.

Therefore, the minimum vessel flange and head flange temperature for bolting is established at 40'F + 60'F or 100 F.

Figures 3.2.2.a, 3.2.2.b, 3.2.2.c, 3.2.2.d, 3.2.2.e, 3.2.2.f and 3.2.2.g have incorporated a temperature shift due to the calculated fast neutron fluence.

The neutron flux at the vessel wall is calculated from core physics data and has been determined using flux monitors installed inside the vessel.

The curves, except for 3.2.2.f and 3.2.2.g, are applicable for up to twenty-eight effective full power years of operation.

Curves 3.2.2.f and 3.2.2.g are applicable for up to twenty and twenty-four effective full power years, respectively.

Vessel material surveillance samples are loc'ated within the core region to permit periodic monitoring of exposure and changes in material properties.

The material sample program conforms with ASTM E185-66 except for the material withdrawal schedule which is specified in Specification 4.2.2.b.

AMENDMENTNO. QE 164 95

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