ML17139B981
| ML17139B981 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 11/02/1983 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17139B982 | List: |
| References | |
| NUDOCS 8311160319 | |
| Download: ML17139B981 (16) | |
Text
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 PENNSYLVANIA POWER AND LIGHT COMPANY LL G
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PER T
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DOCKET NO. 50-387 SUS UEHANNA STE M ELECTRIC STATION, UNIT 1 L
P R
NG L
C NS Amendment No.
17 I ',cer,s"-
I'!o. NPF-14 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The applications for amendments filed by the Pennsylvania Power and Light Company, dated February 3, 1983 and March 11,
- 1983, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 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 Specif-ications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-14 is hereby amended to read as follows:
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.17
, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
PPSL shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
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This amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technica1 Specifications
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Ti A. Schwencer, Chief Licensing Branch No.
2 Division of Licensing Date of Issuance:
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ATTACHMENT TO LICENSE AMENOMENT NO.
17 FCL C
N N
NPF-0 CKET N
0-387 Replace the following pages of the Appendix "A" Technical Specifications with enclosed'pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
REMOVE 2-3 2-4 3/4 2-5 3/4 2-6 3/4 3-53 3/4 3-54 3/4 3-77 3/4 3-78 3/4 3-79 3/4 3-80 INSERT 2-3 2-4 3/4 2-5 3/4 2-6 3/4 3-53 3/4 3-54 3/4 3-77 3/4 3-78 3/4 3-79 3/4 3-80
S'AFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.2 LIMITING SAFETY SYSTEM SETTINGS REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS 2.2.
1 The reactor protection system instrumentation setpoints shall be set consistent with the Trip Setpoint values shown in Table 2. 2. 1-1.
APPLICABILITY:
As shown in Table 3.3.1-1.
ACTION:
I With a rea'ctor protection system instrumentation setpoint less conservative than the value shown in the Allowable Values column of Table 2.2. 1-1, declare the channel inoperable and apply the applicable ACTION statement requirement of Specification 3.3.
1 until the channel is restored to OPERABLE status with its setpoint adjusted consistent with the Trip Setpoint value.
SUS(UEHANNA - UNIT 1 2-3
FUNCTIONAL UNIT TABLE 2.2.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS TRIP SETPOINT ALLOWABLE VALUES 2.
Average Power Range Monitor:
a.
Neutron Flux-Upscale, Setdown b.
Flow Biased Simulated Thermal Power-Upscale 1)
Flow Biased 2)
High Flow Clamped c.
Neutron Flux-Upscale 3.
d.
Inop rative Reactor Vessel Steam Dome Pressure
- High Reactor Vessel Water Level - Low, Level 3
5.
Main Steam Line Isolation Valve - Closure 6.
Main Steam Line Radiation - High 7.
Drywell Pressure
- High 8.
Scram Discharge Volume Water Level High 9.
Turbine Stop Valve - Closure 10.
Turbine Control Valve Fast Closure, Trip Oil Pressure
- Low ll.
Reactor Mode Switch Shutdown Position 12.
Manual Scram l.
Intermediate Range Monitor, Neutron Flux-High
< 120/125 divisions of full scale
< 15K of RATED THERMAL POWER
< 0.58 W+59X, with a maximum of
< 113.5X of RATED THERMAL POWER
< 118X of RATED THERMAL POWER NA
< 1037 psig
> 13.0 inches.above instrument zero*
< 10K closed
< 3.0 x fu11 power background
< 1.72 psig
< 88 gallons
< 5.5X closed
> 500 psig NA
< 122/125 divisions of full scale
< 20X of RATED THERMAL POWER
< 0.58 M<62K, with a maximum of
< 115.5X of RATED THERMAL POWER
< 120K of RATED THERMAL POWER NA
< 1057 psig
> '.'11.5 inches above instrument zero
< 'ill closed
< 3.6 x full power background
< 1.88 psig
<.88 gallons
< ~7X closed
> '460 psig NA NA See Bases Figure B 3/4 3-1.
POWER DISTRIBUTION LIMITS 3/4. 2. 2 APRM SETPOINTS LIMITING CONDITION FOR OPERATION 3.2.2 The APRM flow biased simulated thermal power-upscale scram trip setpoint (S) and flow biased neutron flux-upscale control rod block trip setpoint (SRB) shall be established according to the following relationships:
Tri Set o-',i-st Al 1 owabl e Value S
O.
BW' 59%)T n)
SRB <(0.58W + 50Ã)T SRB
< (0.58W
+ 535)T where:
S and S
B are in percent of RATED THERMAL POWER, W = LooPrecircu1ation fiow as a percentage of the loop recirculation flow which produces a rated core flow of 100 million lbs/hr, T = Lowest va1 ue of the rati o of FRACTION OF RATED THERMAL POWER divided by the MAXIMUM FRACTION OF LIMITING POWER DENSITY.
T is always less than or equal to 1.0.
APPLICABILITY:
OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or RATED THERMAL ER.
ACTION:
With the APRM flow biased simulated thermal power-upscale scram trip setpoint and/or the flow biased neutron flux-upscale control rod block trip setpoint less conservative than the value shown in the Allowable Value column for S or S B, as above determined, initiate corrective action within 15 minutes and adjust 3 and/or S
to be consistent with the Trip Setpoint value within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL PIER to less than 25K of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
SURVEILLANCE RE UIREMENTS
- 4. 2. 2 The FRTP and the MFLPD shall be determined, the value of T calculated, and the most recent actual APRM flow biased simulated thermal power-upscale scram and flow biased neutron flux-upscale control rod block trip setpoints verified to be within the above limits or adjusted, as required:
a.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.
Within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after completion of a THERMAL POWER increase of at least 15K of RATED THERMAL POWER, and c.
Initially and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the reactor is operating with MFLPD greater than or equal to FRTP.
With MFLPD greater than the FRTP during power ascension up to 90K of RATED THERMAL POWER, rather than adjusting the APRM setpoints, the APRM gain may be adjusted such that APRM readings are greater than or equal to 100K times
- MFLPD, provided that the adjusted APRM reading does not exceed 100K of RATED THERMAL POWER, the required gain adjustment increment does not exceed lOX of RATED THERMAL POWER, and a notice of the adjustment is posted on the reactor control panel.
SUSQUEHANNA - UNIT 1 3/4 2-5 Amendment No.
POWER DISTRIBUTION LIMITS 3/4.2.3 MINIMUM CRITICAL POWER RATIO LIMITING CONDITION FOR OPERATION 3.2.3 The MINIMUM CRITICAL POWER RATIO (MCPR) shall be equal to or greater than the MCPR limit determined from Figure 3.2.3-1 times the Kf shown in Figure 3.2.3-2, provided that the end-of-cycle recirculation pump trip (EOC-RPT) system is OPERABLE per Specification 3.3.4.2, with:
A B
tA = 0.86 seconds, control rod average scram insertion time limit to notch 39 per Specification
- 3. 1.3.3, Nl t
= 0.688 + 1.65 [
] (0.052),
1 1 =1 Z
1=1 ave n
Z 1=1 N.T..
1 1,
N.
where:
n = number of surveillance tests performed to date in cycle, N. = number of active control rods measured in the i surveillance
- tests,
.th x,. = average scram time to notch 39 of all rods measured in the i.th surveillance test, and N1 = total number of active rods measured in Specification
- 4. 1. 3. 2. a.
APPLICABILITY:
OPERTIONAL CONDITION 1, when THERMAL POWER is greater than or equal to 25K of RATED THERMAL POWER.
SUSQUEHANNA - UNIT 1 3/4 2-6
TABLE 3.3.6-1 (Continued)
CONTROL ROD BLOCK INSTRUMENTATION ACTION ACTION 60 Declare the RBM inoperable and take the ACTION required by Speci ficati on 3. 1. 4. 3.
ACTION 61 With the number of OPERABLE Channels:
a 0 One less than required by the Minimum OPERABLE Channels per Trip Function requirement, restore the inoperable channel to OPERABLE status within 7 days or place the inoperable channel in the tripped condition within the next hour.
b.
Two or more less than required by the Minimum OPERABLE Channels per Trip Function requirement, place at least one inoperable channel in the tripped condition within one hour.
ACTION 62 With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, place the inoperable channel in the tripped condition within one hour.
NOTES With THERMAL POWER > 30K of RATED THERMAL POWER.
a.
With move than one control rod withdrawn.
Not applicable to control rods removed pev Specification 3.9. 10.
1 or 3.9. 10.2.
The RBM shall be automatically bypassed when a peripheral control rod is selected or the reference APRM channel indicates less than 30K of RATED THERMAL POWER.
b.
C.
d.
e.
This function shall be automatically bypassed if detector count rate is 100 cps or the IRM channels are on range 3 ov higher.
This function shall be automatically bypassed when the associated IRM channels are on range 8 or higher.
This function shall be automatically bypassed when the IRM channels are on range 3 or higher.
This function shall be automatically bypassed when the IRM channels are on range l.
SUSQUEHANNA - UNIT 1 3/4 3-53
TABLE 3.3.6-2 CONTROL ROD BLOCK INSTRUMENTATION SETPOINTS TRIP FUNCTION 1.
ROD BLOCK MONITOR TRIP SETPOINT ALLOWABLE VALUE a.
Upscale b.
Inoperative c.
Downscale
< 0.66 W + 40K
< 0.66 W+ 43K NA NA
> 5/125 divisions of full scale
> 3/125 of divisions full scale 2.
3.
APRM a.
Flow Biased Neutron Flux - Upscale b.
Inoperative c.
Dowrscale d.
Neutron Flux - Upscale Startup SOURCE RANGE MONITORS
- a. 'etector not ful.l in b.
Ups cal e c.
Inoperative d.
Downscale
< 0.58 W + 50@*
NA
> 5X of RATED THERMAL POWER 12K of RATED THERMAL POWER NA<2x10 cps NA
) 3 cps*A
< 0.58 W+53X*
NA
> 3X of RATED THERMAL POWER
< 14K of RATED THERMAL POWER NA
< 4 x 10 cps NA
) 2 cps%'A'.
INTERMEDIATE RANGE MONITORS a.
b.
C.
d.
Detector not full in Upscale Inoperative Downscale NA
< 108/125 divisions of full scale NA
> 5/125 divisions of full scale NA
< 110/125 d'.visions of full scale NA
> 3/125 divisions of full scale 5.
Water Level High
< 44 gallons
< 44 gallon"-
6.
REACTOR COOLANT SYSTEM RECIRCULATION FLOW a.
Upscale
< 108/125 divisions of full scale ill/125 divisions of full scale b.
Inoperati ve NA NA c.
Comparator
< 10K flow deviation llew flow deviation "The Average Power Range Monitor rod block function is varied as a function of recirculation loop flow (W).
The trip setting of this function must be maintained in accordance with Specification 3.2.2.
- "For initial loading and startup the count rate may be
> 0.5 cps.
INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.9 As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 3.3.7.9-1 shall be OPERABLE.
APPLICABILITY:
Whenever equipment protected by the fire detection instrument is required to be OPERABLi.
ACTION:
With the number of OPERABLE fire detection instruments less than the Minimum Instruments OPERABLE requirement of Table 3. 3. 7. 9-1:
a.
Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, establish a fire watch patrol to inspect the zone(s) with the inoperable instrument(s) at least once per hour, unless the instrument(s) is located inside an inaccessible
- zone, then inspect the area surrounding the inaccessible zone at least once per hour.
b.
Restore the minimum number of instrument(s) to OPERABLE status within 14 days or, in lieu of any other report required by Specification 6.9. 1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the instrument(s) to OPERABLE status.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE RE UIREMENTS
- 4. 3. 7. 9. 1 Each of the above required fire detection instruments which are accessible during unit operation shall be demonstrated OPERABLE at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST.
Fire detectors which are not accessible during unit operation shall be demonstrated OPERABLE by the performance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless performed in the previous 6 months.
4.3.7.9.2 The supervised circuits supervision associated with the detector alarms of each of the above required fire detection instruments shall be demonstrated OPERABLE at least once per 6 months.
SUSQUEHANNA - UNIT 1 3/4 3-77
INSTRUMENT LOCATION TABLE 3. 3. 7. 9-.1 FIRE DETECTION INSTRUMENTATION INSTRUMENTS OPERABLE FIRE ZONE ROOM OR AREA HEAT ELEV.
TOTAL MIN.
PHOTO-IONIZATION ELECTRIC TOTAL MIN.
TOTAL MIN.
a.
Control Buildin 0-24D 0-240 0-25A 0"25E 0"26H 0-26H 0-26H 0-26H 0-27C 0" 27B 0-27E 0-27E 0"28K 0-28L 0-28M 0-28N 0-28I 0-28J
.0-28G 0-28F 0-28E 0"28C 0-28D 0-28T Lower Relay Room PGCC Lower Cable Spreading Rm.
Lower Cable Spreading Rm.
Control Rm.
(Under Flr. Unit 1)"
Control Room (Under Flr. Unit 2)*
Control Room Control Rm.
(Above Clg)*
Upper Cable Spreading Rm.
Upper Cable Spreading Rm.
Upper Relay Room PGCC Battery Room Battery Room Battery Room Battery Room Battery Room Battery Room Battery Room Battery Room Battery Room Battery Room Battery Room Battery Room 698'1" 4
2 698'-1" 54 27 714'"0" 26 13 714 I -O'I 20 10 729'-1" NA NA 753'-0" 29 14 753'-0" 754'"1" 754 I 1 II 771 I 0ll 771l "0" 771'-0" 771'-0" 771'-0" 771I -0"
, 771'0" 771'0" 771'-0" 771'-0" 771 I Oll 771'-0" 28 14 4
2 55 27 NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA 729'"1" NA NA 729'-1" NA NA 729'"1" NA NA 4
2 30 15 6
3 6
3 18 9
15 7
10 5
9 4
8 4
5 2
2 1
30 15 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 NA NA NA NA NA NA NA NA NA, NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA SUSQUEHANNA - UNIT 1 3/4 3-78 Amendment No.
17
TABLE 3.3.7.9-1 (Continued)
FIRE DETECTION INSTRUMENTATION INSTRUMENT LOCATION--
FIRE ZONE ROOM OR AREA INSTRUMENTS OPERABLE PHOTO-HEAT IONIZATION ELECTRIC ELEV.
TOTAL MIN.
TOTAL MIN.
TOTAL MEN.
1"4C 1-4D 1-4A 1-SF 1-5G 1-2A 1"3A 1-3B 1-3C 1-4B 1-4G 1-5B 1"5D 1-6A 1-6I Switchgear Room Switchgear Room Containment Access Area Load Center Room Load Center Room Access Area Access Area Access Area Access Area Pipe Penetration Room Main Steam Piping Valve Access Area RWCU Pumps 8 Heat Exchangers Penetration Room Access Area Fuel Pool Holding Pump Room b.
Reactor Buildin 1-1B Core Spray Pump Room 1-1A Core Spray Pump Room 1-lE RHR Pump Room 1-1F RHR Pump Room 1-1D RCIC Pump Room 1-1C HPCI Pump Room 1-1G Sump Room 1-2D Remote Shutdown Panel Rm.
645'-O" 645'"0" 645'-0" 645'-0" 645'-O" 645'-O" 645'"0" 67O'-O" 719 I
OII 719 I
Oll 719'-0" 749'-1" 749'-1" 670'-0" 683'"0" 683'-0" 683'"0" 719'-1" 719'-1" 761'-1O" 749 I
1 II 749 '1" 779 I 1 II 779'-1" NA NA NA NA NA NA NA NA 2
1 2
1-.
NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA 5
2 7
3 NA NA NA NA NA NA NA NA 2
1 2
1 2
1 2
1 27 13 2
1 2
1 7
3 7
3 12 6
NA NA 1
1 NA NA NA NA NA NA NA NA 9
4 NA NA NA NA NA NA 13 7
15 8
5 2
7 3
NA NA NA NA NA NA NA NA 4
2 NA NA NA NA NA NA NA NA NA NA 13 6
NA NA 6
3 2
1 12 6
2 1
NA NA 2
1 SUS(UEHANNA - UNIT 1 3/4 3-79 Amendment No. 17
FIRE ZONE Reactor INSTRUMENT LOCATION ROOM OR AREA Buildin
'Continued TABLE 3.3.7.9-1 (Continued)
FIRE DETECTION INSTRUMENTATION INSTRUMENTS OPERABLE PHOTO-HEAT IONIZATION ELECTRIC ELEY.
TOTAL MIN.
TOTAL MIN.
TOTAL MIN.
1-6D 1-6E 0-6G 1-7A
'0-8A H&V Equipment Room Recirculation Fans Area Surge Tank Vault H&V Fan and Filter Rooms Refueling Floor 779'"1<<
NA NA 779'-1<<
NA NA 779'"4<<
NA NA 799'<<24 1 2 818'1<<NA NA 12 6
2 1
2 1
15 7
NA NA NA HA NA NA NA NA 30 15
. i':~E 0-51 0-52 Pump Room Pump Room 685'"6<<
NA NA 685'-6<<
NA NA 6
3 6
3 INFRA"RED (FLAME)
TOTAL MIN.
NA NA NA HA d.
Diesel Generator Buildin 0-41A Diesel Generator Rooms 0-41C Diesel Generator Rooms 0-41B Diesel Generator Rooms 0-41D Diesel Generator Rooms 660'"0<<
677'-0<<
660'-0<<
677'"0<<
660'-0<<
677'-0<<
660'-0<<
677'-0<<
22 ll 22 ll ll 22 11 2
1 2
1 2
1 2
1 15 7
15 7
15 7
15 7
Not accessible.
SUSQUEHANNA - UNIT 1 3l4 3-80 Amendment Ho.
17