ML20202B992
| ML20202B992 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 11/25/1997 |
| From: | Berkow H NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20202B997 | List: |
| References | |
| NUDOCS 9712030234 | |
| Download: ML20202B992 (9) | |
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4 UNITED STATES
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NUCLEAR REGULATORY COMMISSION c
WASHINGTON. D.C. 9004H001 s,...../
DUKE ENERGY CORPORATION DOCKET NO. 5(E369 McGUIRE NUCLEAR STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSr; Amendment No. 177 License No. NPF 9 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the McGuire Nuclear Station, Unit 1 (the facility), Facility Operating License No. NPF 9 filed by the Duke Energy Corporation (licensee) dated October 13,1997, as supplemented by letters dated October 28 and November 5,1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as 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 activitles authorized by this amendment can b6 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 set forth in 10 CFR Chapter I; 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 thia amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
9712030234 971125 PDR ADOCK 05000349 p
4 2-2.
Accordingly, the license is hereby amended by pags changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paracraph 2.C.(2) of Facility Operating License No. NPF g is hereby amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 177, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications.
i 3.
This license amendment is effective as of its date of issuance and shall be implemented consistent with the refueling outage scheduled for June 1998.
FOR THF WUCLEAR REGULATORY COMMISSION
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L H rbert N. Berkow, Director Project Directorate ll 2 Division of Reactor Projects - 1/ll Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
November 25, 1997 G
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ATTACHMENT TO LICENSE AMENDMENT NO 177 FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 l
Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Remove jnand 3/4331 3/4 3-31 B 3/413 8 3/4 1 3 i
f
..,,,,.... _,, -,, -, ~...,,-.
5 7
TABLE 3.3-4 " Con-inuedl ENGINEEED SAF*TY FEATURES AC1UATION SYSTEN IRSTRtENTATIC41 TRIP SETP91NTS TRIP SETPOIN1 ALLOWAE.E TAL1ES p
FUNCTIOML WUT 7.
Auxiliary feedwate- (contiwed) 7 f.
Station Blackout - Start Motor-Driven Pumps and R
Tertime-Daiven Pump (kte 1)
- 1) 4 kV Loss of Voltage 3174 i 45 volts with a 2 3122 volts 1
8.5 1 0.5 setend time delay
- 2) 4 <V Degra$ed foltage
> 3678.5 volts with i 11 2 3661 volts r
second with SI and s 600 second without SI time delays t
g.
T-1p of Main Feeddater Ptsups -
N.A.
M.A.
Start Motar-Driven Pays 8.
Automatic SwitchcVer to Recirculation RitST _evel 2 ISC inches 2 175.85 inches 1
9.
Loss of Poser a.
4 kV toss of Voltage
~174 i 45 volts with a a 3122 volts 8.5
- 0.5 second time de'ay b.
4 kV Degraded Voltage 2 3678.5 volts w;th s 11 2 3661 volts 6
second with SI and s 600 second without 5: tine delays
- 10. Engineered Safety Features Actuation L
System Interlocks a.
Pressurizer Pressure. P-11 1 1955 psig s 1965 psig
]
z 553*F 1 551*F b.
Tm. P-12 c.
Reactor Trip, P-4 E.A.
N.A.
i d.
Stear Generator Level, P-14 See Item Sb. above for all Trip 5etpoints and Allowable Values.
Note 1: The turbine driver pump will not start on a b'ackout sign 31 coincident with a safety injection signal.
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McGUIRE - UNIT 1 3/43-31 Amendment No. 177
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REACIIVITY CONI 41.1YSTEMS natrt t0kATIONSYiIEM$(Continued)
Refuelina Water Starace Tank kanuirements for Maintainina 1DM Modet 1-4 Required volume for maintainin Unusable volume (below nortle)g SDN presented in the COLR 16,000 gallons Additional margin 23.500 gallons l
With the RC5 temperature below 200'f. one Boron Injectio9 System is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATION 5 and positive reactivity changes in the event the single Baron Injection System becomes (noperable.
The limitation for a maximum of one centrihfe, d u M pump to be OPERA 8tt and the surveillance Requirement to verP!r on cht.rging pumps except 4
i the required OPERABLE pump to be inoperable below h4 wovides assurance that a mas 1 addition pressure transient can be relieved by tne operation of a single PORV. Allowing two Centrifugal Charging pugs to operate simultaneouviy for s15 minutes increases the martin of safety with respect to the Reactor Coolant pump seal failure resulting in a LOCA in that the Reactor Coolant pump seal injection flow is not interrupted during pug swap. For the 15 minute period during which simultaneous Centrifugal Charging pump operation is allowed, the safety margins as related to the mass addition analysis are not appreciably reduced. Technical Specification 3.4.9.3 requires two PORys to be o>erable during this period of operation, thus a mass addition transient can >e relieved 1
as required assuming the two PORVs function properly.
The boron capability required below 2004 is suff tetent to provide a 5HUTDOWN MARGIN of 1% delta k/k after xenon decay and cooldown from 2004 to 140 7. The minimum borated water volumes and concentrations required to maintain shutdown margin for the Boric Acid Storage System and the Refueling Water storage Tank are presented in the Core Operating Limits Report.
The Technical Specification LC0 value for the Soric Acid $ tor.ge Tank and the Refueling Water 5torage Tank minimam contained water volume during Modes 5 and 8 is based on the required volume to maintain shutdown margin, an allowance for unusable volume and additional margin as follows:
aarie Aefd Starace Tank Recuirements foe Maintainine IDM - Modet 5 1 8 Required volume for maintaining $DN presented in the COLR i
Unusable volume (to maintain full suction pipe) 4,199 gallons Additional mergin 4,100 gallons llafueline Water Storace Tank Reautrements for Maintainino SDN - Moden 5 & 6 Required volume for maintainin presented in the COLR Unusable volume (below norrie)g SDM 16,000 gallons 1
i Additional margin 23.500 gallons l
j McGUIRE UNIT 2 B3/41-3 Amendment No. 177
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t UNITE 3 STATES j
,j NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D.C. 3066H001 DUKE ENERGY CORPORATION QQCEE.T NO. 50-370 McGUIRE NUCLEAR STATION. UtiLT_2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 159 License No. NPF 17 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the McGui;e Nuclear Station, Unit 2 (the facility), Facility Operating License No. NPF-17 filed by the Duke Energy Corporation (licensee) dated October 13,1997, as supplemented by letters dated October 28 and November 5,1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules arid r9pulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the ap,nlication, the provisions of the Act, and the rules and iegulations of the Commission; C,
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangerir'g the health and. safety of the public, and (ii) that t.ch activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; 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 tegulations and all applicable requirements have been satisfied.
l i
_... _ _ _ _. _ _ - _ _ =. _ _ _. _. _ _. _
i 2.-
2, Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this licer.se amendment, and Paragraph i
2.C.(2) of Facility Operating License No. NPF 17 is hereby amended to read as follows:
(2) Technical Soecifications
- The Technical Specifications contained in Appendix A, as revised through Amendment No. 159, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR Tete NUCLEAR REGU'.ATORY COMMISSION do Herbett N. Berkow, Director Project Directorate 112 Division of Reactor Projects 1/11 Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of lasuance:
November 25, 1997 l
I ATTACHMENT TO LICENSE AMENDMENT NO.159 FACILITY OPERATING LICENSE NO. NPF-17 DOCKET NO. 50 370 t
Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain verticallines indicating the areas of change.
Remove Insert t
3/4 3-31 3/4 3-31 B 3/4 1 3 B 3/4 1-3 9
Y t
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TA3tE 3.3-4 (Continuedl DiGINEERED SAFITY EMURES ACTUATION SYSTD4 INSTRUMEhfATION TRIP SETPOINTS h
FUNCTIOEAL UNIT TRIP SETPOINT ALLOWABLE YALUES 5
7.
Auxiliary Feedwater (cantirwed) f.
Station Blackout - Start a
Motor-Driven hans and Terbine-D-ive) Pug (Note 1)
- 1) 4 kV Loss af V31tage 3157 1 45 volts with a a 3108 vol:s f
8.5
- 0.5 second tirn delay
- 2) 4 kV Degra$ed Voltage 2 3703 relts with 5 11 2 3685.5 volts g
ce second with SI and s 600 second withott 51 time delays e
E g.
Trip of Main Feedwater Pumps -
6.A.
N.A.
5';&rt Motor-Driven Pays 8.
Autesatic Swit: hover to Recirculation RNST Level 2 18C inches
> 175.85 inches 9.
Loss of Power a.
4 kV '_oss of Voltage 3157 1 45 volts with a
> 3108 volts 8.5
- 0.5 second time de'ay b.
4 kV 3egraded Voltage a 3703 volts with s 1 z 3685.5 volts second with 'I and s 600 second without SI tine delays
- 10. Enginerred Safety Features Actuation System Interlocks a.
Pressurizer Pressure, P-11
< 1955 psig s 1%5 psig 2 553*f 2 551*F b.
T,,,, P-12 c.
Reactor Trip, P-4 R.A.
N.A.
d.
Steam Generator level. P-14 See Item Sb. above for all T-ip Setp31nts and Allowable Yalues.
Note 1:
The turbine driven ptmp will not start on a blackout signal coincident with a safety infection' signal.
McGJIRE - IMIT 2 3/43-31 Anendnent No.159 c,
2 O
KAtTWITY CONTROL SYtTuti maarn acAAttom SYSTEMS (Continued) esfuelina Watee Sierace Tank Ranoirements for Maintainine RDM. Madas 1-a i
Required volume for maintaining 304 presented in the COLR Unusable volume (below nozzle) 16.000 gallons Additional margin 13.800 gallons l
With the RC5 temperature below 200'F. one Boron Injection System is acceptable without single failure consideration on the basis of the stable reactivity condition of the reMtor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity changes in the event the single goron Injection System becomes inoperable.
The limitation for a maximum of one cenWwal charging pump to be OPERABLE and the Surveillance Requirement to verify all ciar0ing pumps except the required OPERABLE pump to be inoperable below 300'F prov' des assurance tnat a mass addition pressure transient can be relieved by the operation of a single PORV. Allowing two Centrifugal Charging pungs to operate simultaneously for
$15 minutes increases the margin of safety with respect to the Reactor Coolant pump seal failure resulting in a LOCA in that the Reactor Coolant pump seal injection flow is not interrupted durin<3 pump swap. For the 15 minute period during which simultantovs Centrifugal C)arging pump operation is allowed, the safety marp'echnical Specift::ation 3.4.g.3 requires two PORVs to be operable ins as related to the mass addition analysis are not appreciably reduced.
during this period of operation, thus a mass tddition transient can se relieved as required assuming the two PORVs function properly.
The boron capability required below 200*F is sufficient to provide a
$HUTD0WN MARGIN of 14 delta k/k af ter renon decay and cooldown from 200*F to 140'F. The minimuir borated water volu'nes and concentrations required to maintain shutdown margin for the Boric Acid $torage System and the Refueling Water storage Tank are presented in the Core Operating Limits Report.
The Technical Specification LC0 value for the Boric Acid Storage Tank and the Refueling Wter Star;ge Tank minimum contained water volume during Modes 5 and 6 is based on the required volene to maintain shutdown margin an allowance for unusable volume and additional margin as follows:
ancie Acid sterane Tanir Ranuiemments for Maintaintne EDM - Madas a 18 Required volume for maintaining SDM presented in the COLR Unusable volume (to maintain full suction pipe) 4.199 gallons Additional margin 4.100 gallons Refueline Water Storama Tank Ranuiemments far Maintainino SDhi - Madma B 1 &
Required volume for maintaining SDN presented in the COLR Unusable volume (below nozzle) 16.000 gallons Additional margin 23.s00 gallons l
McGUIRE - UNIT 1 B3/41-3 Amendment No'.159 e en -
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