ML20217K819
| ML20217K819 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 10/21/1999 |
| From: | Emch R NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217K822 | List: |
| References | |
| NUDOCS 9910260249 | |
| Download: ML20217K819 (10) | |
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- t UNITED STATES ll j
NUCLEAR REGULATORY COMMISSION
'2 W ASHINGToN. D.C. 2055%X)01
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l-SOUTH CAROLINA ELECTRIC & GAS COMPANY l
SOUTH CAROLINA PUBLIC SERVICE AUTHORITY l
DOCKET NO. 50-395 VIRGIL C. SUMMER NUCLEAR STATION. UNIT NO. I AMENDMENT TO FAOILITY OPERATING LICENSE j
Amendment No.143 License No. NPF-12 i
l 1.
The Nuclear Regulatory Commission (the Commission) has found that:
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A.
The application for amendment by South Carolina Electric & Gas Company (the licensee), dated August 19,1999, as supplemented by letter dated October 8,
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1999, complies with the standards and requirements of the Atomic Energy Act of j
1954, as amended (the Act), and the Commission's rules and regulations set i
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 sssurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the i
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 rag'Micris 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-12 is hereby amended to read as follows:
9910260249 991021 PDR ADOCK 05000395 P
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,T hnical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through-Amendment No. :143, and the Environmental Protection Plan contained in
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Appendix B, are hereby incorporated in the license South Carolina Electric & Gas l
Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
l 3.
This amendrnent is effectiv'e es of the date of issuance.
i l-FOR THE NUCLEAR REGULATORY COMMISSION
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l-Richard L. Emch, Jr., Chief, Section 1 Project Directorate 11 Division of Licensing Project Management l
Office of Nuclear Reactor Regulation t
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Attachment:
Changes to the Technical
- Specifications l
Date of Issuance: October 21,.1999 G
ATTACHMENT TO LICENSE AMENDMENT NO.143 TO FACILITY OPERATING LICENSE NO. NPF-12 DOCKET NO. 50-395 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginallines indicating the areas of change.
Remove Paaes insert Paaes Xill XIll 3/4 4-31 3/4 4-3t 3/4 4-32 3/4 4-32 B 3/4 4-6 8 3/4 4-6 B 3/4 4-7 83/44-7 4
8 3/4 4-8 B 3/4 4-9 B 3/4 410 8 3/4 4-10a B 3/4 4-11 B 3/4 4-12 B 3/4 4-13 B 3/4 4-14 83/44-14 I
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INDEX BASES SECTION PAGE 3/4.4.5
- STEAM G EN ERATORS......................................
... B 3/4 4 3 3/4.4.6
-~ REACTOR COOLANT SYSTEM LEAKAGE........................... B 3/4 4-4 c 3/4.4.7 C H E M I STR Y....................................,................................. B 3/4 4 - 5 3/4.4.8?
, c SPECIFIC ACTIVITY...........................
.. B 3/4 4-5 3/4.4.9 PR ESSU R E/TEMPERATU R E LlMITS.......................................... B 3/4 4-6 3/4.4.10
' STRUCTURAL INTEGRITV
............. B 3/4 4-15 3/4.5 EMERGENCY CORE COOLING SYSTEM (ECCS) 3/4.5.1 AC C U M U LATO R S................................
.................... B 3/4 5-1 3/4.5.2 and 3/4.5.3 ECCS SU BSYSTEM3............................................... B 3/4 5-1 3/4.5.4
' REFUELING WATER STORAGE TANK (RWST)........................ B 3/4 5-2 1
3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAI N MENT.......................................................... B 3/4 61 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS....................... B 3/4 6-3 3/4.6.3 PARTICULATE IODINE CLEANUP SYSTEM..................................... B 3/4 6-4 3/4.6.4 CONTAINMENT ISOLATION VALVES........................................... B 3/4 6-5 3/4.6.5'-
COMBUSTIBLE G AS CONTROL..................................................... B 3/4 6-5 L
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I SUMMER - UNIT 1
' XIll Amendment No. 447 143
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BEACTOR COOLANT SYSTEM MATERIAL PROPERTY BASIS' LIMITING MATERIAL: LOWER SHELL PLATES C9923-1,-2 LIMITING ART VALUES AT 32 EFPY:
1/4T, 107 F 3/4T, 94 F 2500 r
2250 l
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-l LEAK TEST LIMIT I
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2000 HEATUP RATE i
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UP TO SO F/Hr.
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7U ATE UNACCEPTABLE p,.
OPERATION r
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ACCEPTABLE'
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i OPERATION 1 50 l
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CRIT. LIMIT t
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1000 -
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FOR 50 F/Hr.
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CRIT, LIMIT q
750 FOR 100 F/Hr.
U T-s 500
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Bott Up N
' G; Temp CRITICALITY LIMIT BASED ON l
250 INSERVICE HYDROSTATIC TEST TEMPERATURE (164*F) FOR THE SERVICE PERIOD UP TO 32.0 EFPY Ill Illi Illi Illi II 0
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50 100 150 200 250 300 350 400 450 500 Moderator Temperature ( F)
I i-Figure 3.4-2 V. C. Summer Unit 1 Reactor Coolant System Heatup Limitations (Heatup rates up to 50 and 100 F/hr) Applicable for the First 32 EFPY
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(Without Margins for Instrumentation Errors) 1 SUMMER _- UNIT 1 3/4 4-31 Amendment No. 53M1SH33,143 )
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HEACTOR COOLANT SYSTEM MATERIAL PROPERTY BASIS LIMITING MATERIAL: LOWER SHELL PLATES C9923-1, -2 LIMITING ART VALUES AT 32 EFPY:
1/4T, 107. F 1
3/4T, 94 F l
2500 i
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2250 i
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- UN '.CCEPTABLE a 2000 -: OPERATION i
To Tn 1750 i
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1500
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2 COOLDOWN
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g 1250 -: RATES y
- F / Hr.
o ACCEPTABLE E.1000 OPERATION 3
3 50 750 -333. 100 U
500 T
Rolt Up
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0 50 100. 150 200 250 300 350 400 450 500 i
Moderator Temperature ( F)
Figure 3.4-3 V. C. Summer Unit 1 Reactor Coolant System Cooldown Limitations (Cooldown Rates of 0,25,50 and 100 F/hr) Applicable for the First 32 EFPY (Without Margins for Instrumentation Errors) 1 1
SUMMER - UNIT 1 3/4 4-32 Amendment No. 53rHSr193,14
C.l O
BASES SPECIFIC ACTIVITY.(Continued)
The ACTION statement permitting POWER OPERATION to corbnue for limited time periods with the primary coolant's specific activity greater than 1.0 microcuries/
gram DOSE EQUlVALENT l 131, but within the allowable limit shown on Figure 3.4-1,-
accommodates possible iodine spiking phenomenon which may occur following changes in THERMAL POWER.
I Reducing TW to less than 500 F prevents the release of activity should a steam generator tube rupture since the saturation pressure of the primary coolant is below the lift pressure of the atmospheric steam relief valves. The surveillance requirements provide adequate assurance that excessive specific activity levels in the primary coolant will be detected in sufficient time to take corrective action. Information obtained on iodine spiking will be used to assess the parameters associated with spiking phenomena. A reduction in frequency of isotopic analyses following power changes may be permissible if justified by the data obtained.
3/4.4.9 PRESSURE / TEMPERATURE LIMITS
- The temperature and pressure changes during heatup and cooldown are limited by curves cleveloped using the methodology from Westinghouse Topical Report, WCAP-14040-NP A, updated to include the requirements of the 1996 ASME Boiler and Pressure Vessel Code,Section XI, Appendix G along with ASME Code Case N-640.
1)
The reactor coolant temperature and pressure and system heatup and cooldown rates (with the exception of the pressurizer) shall be limited in accordance with Figures 3.4-2 and 3.4-3.
a)
Allowable combinations of pressure and temperato(e for specific temperature change rates are below and to the ;ht of the limit lines shown. Limit lines for cooldown rates between those presented may be obtained by interpolation.
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J SUMMER - UNIT 1
~ B 3/4 4-6 Amendment No. 53r64143
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, _ BASES l
PRESSURE / TEMPERATURE LIMITS (Continued)
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Figures'3.4-2 and 3.4-3 define limits to assure prevention of non-ductile failure only. For normal operation, other inherent plant characteristics,
.e.g., pump heat addition and pressurizer heater capacity, may limit the '
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heatup and cootdown rates that can be achieved over certain pressure-temperature ranges.
2).
_These limit lines shall be calculated periodically using methods acceptable to the NRC.
-. 3)
The secondary side of the steam generator must not be pressurized above 200 psig if the temperature of the steam generator is below 70 F, 4)
The pressurizer heatup and cooldown rates shall not exceed 100'F/hr and 200*F/hr respectively. The spray shall not be used if the temperature difference between the pressurizer and the spray fluid is greater than 625 F.
5)-
System in-service leak and hydrotests shall be performed at pressures in I
accordance with the requirements of ASME Boiler and Pressure Vessel Code,Section XI.
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I SUMMER - UNIT _1 B 3/4 4-7 Amendrnent No. 63r 143 l
BASES-The following Pages have been deleted:
S 3/4 4-8 8 3/4 4-9 B S/4 4-10
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B 3/4 4-10a j
B 3/4 4-11 B 3/4 4-12 B 3/4 4-13 SUMMER - UNIT 1 B 3/4 4-8 Amendment No. 63r 143
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lu-b REACTOR COCLANT SYSTENI.
BASES I
PRESSURE / TEMPERATURE LIMITS (Continued)
I Limit curves for normal heatup and cooldown of the primary Reactor Coolant l
System have been calculated as described in Westinghouse Topical Report, WCAP-15102, Rev. 2 "V. C. Summer Unit 1 Heatup and Cooldown Curves for Normal Operation".
Transition temperature shifts occurring in th'e pressure vessel materials due to
, radiation exposure have been obtained directly from the reactor pressure vessel surveillance program. Charpy test specimens from Capsule W indicate that the core region lower shell plate code no. C9923-1, -2 are the limiting beltline materials for all heatup and cooldown curves to be generated. These materials exhibit limiting ART values of 107 F at 1/4T and 94 F at 3/4T at a calculated inner surface fluence of 3.84 x 10" n/cm at 32 EFPY.
2 Allowable combinations of temperature and pressure for specific temperature change rates are below and to the right of the limit I:nes shown on the heatup and cooldown curves. The reactor must not be made critical untii pressure-temperature combinations are to the right of the criticality limit line shown in Figure 3.4-2. This is in 1
addition to other criteria which must be met before the reactor is made critical, as 1
discussed in the following paragraphs.
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The leak test limit curve shown in Figure 3.4-2 represents minimum temperature requirements at the leak test pressure specified by applicable codes. The leak test limit curve was determined by methods of the Standard Review Plan, Chapter 5.3.2 and l
Appendix G of the ASME Code,Section XI.
j The reactor must not be made critical until pressure-temperature combinations are to the right of the criticality limit line shown in Figure 3.4-2. The criticality limit curve i
specifies pressure - temperature limits for core operation to provide additional margin during actual power production as specified in Appendix G to 10 CFR 50. The pressure
- temperature limits for core operation (except for low power physics tests) are that the reactor vessel must be at a temperature equal to or higher than the minimum temperature required for the inservice hydrostatic test, and at least 40 F higher than the l
minimum permissible temperature in the corresponding pressure - temperature curve for heatup and cooldown calculated as described in this technical basis..The vertical i
line drawn from these points on the pressure - temperature curve, intersecting a curve
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40 F higher than the pressure - temperature limit curve, constitutes the limit for core operation for the reactor vessel.
. Figures 3.4 2 and 3.4-3 define limits for insuring prevention of nonductile failure.
The instrument uncertainties, effects of forced flow from the reicter coolant j
pumps, and the eievation effect of the pressure sensors are incorporated into the curves located in the plant operating procedures.
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. SUMMER - UNIT 1 B 3/4 4-14 Amendment No. 6& 143
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