ML17139C425
| ML17139C425 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 05/23/1984 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17139C426 | List: |
| References | |
| NUDOCS 8406050029 | |
| Download: ML17139C425 (16) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMlSSION WASHINGTON, D. C. 20555 PENNSYLVANIA POWER
& LIGHT COMPANY ALLEGHEN L
C C
C PER IN.
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5 -387 USUEANA ~LE C
TON Nl 1
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N C L Y
P R
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NSE Amendment No.
23 License No. 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 Light Company, dated October 11, 1983; October 24, 1983; and November 4, 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 comon 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 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.23
, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
PP&L shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
8406050029 840523 PDR ADOCK'05000387,...
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This amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COlltiISSION g.Wuv ~~
A. Schwencer, Chief L'icensing Branch No.
2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
MAY 2 3 Qg
ATTACHMENT TO LICENSE AMENDMENT NO. 23 C
. 50-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 3/4 3-11 3/4 3-12 3/4 6-19 3/4 6-20 3/4 6-21 3/4 6-22 3/4 6-23 3/4 6-24 3/4 7-3 3/4 7-4 3/4 7-9 3/4 7-10 INSERT 3/4 3-11 3/4 3-12 3/4 6-19 3/4 6-20 3/4 6-21 3/4 6-22 3/4 6-23 3/4 6 3/4 7-3 3/4 7-4 3/4 7-9 3/4 7-10
TABLE 3.3.2-1 ISOLATION ACTUATION INSTRUMENTATION TRIP FUNCTION 1.
PRIMARY CONTAINMENT ISOLATION a.
Low, Level 3
MINIMUM APPLICABLE ISOLATION OPERABLE CHANNELS OPERATIONAL
)( )
1,2,3 ACTION 20 2)
Low Low, Level 2
3)
Low Low Low, Level I b.
Drywell Pressure
- High c.
Manual Initiation B
X Y,Z,X NA 2
2 2
1,2,3 I, 2, 3
1, 2, 3
1 2
3 20 20 20 24 2.
SECONDARY CONTAINMENT ISOLATION a.
b.
C.
d.
e.
Reactor Vessel Water Level-Low Low, Level 2
Y Drywell Pressure High Y,Z {c)
Refuel Floor High Exhaust Duct Radiation - High Railroad Access Shaft Exhaust Duct Radiation - High Refuel Floor Wall Exhaust Duct Radiation - High Manual Initiation 1,2,3and*
1, 2, 3
1, 2, 3 and "
1,2,3and" 1,2,3and*
1, 2, 3 and
- 25 25 25 25 25 24
TABLE 3.3.2-1 (Continued)
ISOLATION ACTUATION INSTRUt1EHTATIOH TRIP FUNCTION MIN ItIUD APPLICABLE ISOLATION( )
'OPERABLE CHANNELS OPERATIONAL SIGNAL(s)
PER TRIP SYSTEM (b)
CONDITION ACTION 3.
4.
t1AIN STEAM LINE ISOLATION a.
Reactor Vessel Mater Level-Low, Low, Level 2
b.
Main Steam Line Radiation High c.
Main Steam Line Pressure Low d.
e.
Main Steam Line Flow - High 0
Condenser Vacuum - Low UA NA f.
Main Steam Line Tunnel Temperature - High g.
Main Steam" Line Tunnel h Temperature - High h.
Manual Initiation REACTOR WATER CLEANUP SYSTEM ISOLATION 2
2/line 2/1 ine 1
2 3
1 2
3 1
2 3
1 2
3 1
2 3
1 2
3 1
2 3
21 21 22 20 21 21 21 24 a.
b.
d.
g.
RWCS h Flow - High RWCS Area Temperature High RWCS Area Ventilation g Temp.
High SLCS Initiation Reactor Vessel Water Level - Low Low, Level 2
RWCS z Pressure
- High t1anual Initiation (d)
J HA NA 2
1,2,3 1,2,3 1
2 3
1,2,3 1
2 3
1 2
3 1,2,3 23 23 23 23 23 23 24
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TABLE 3. 6. 3-1 I
PRIMARY CONTAINMENT ISOLATION VALVES VALVE FUNCTION AND NUMBER a.
Automatic Isolation Valves MSIV HV-141F022 A,B,C) D HV"141F 028 A,8, C, D MSL Drain HV"141F 016 HV-141F019 RCIC Steam Su 1
HV-149F007 HV-149F008(')
HV-149F088 HPCI Steam Su 1
HV-155F002 HV-155F003(')
HV-155F100 RHR - Shutdown Coolin Suction HV-151F008 HV-151F009 MAXIMUM ISOLATION TIME Seconds 10 10 20 20 3
50 50 3
52 52 ISOLATION( )
SIGNAL s
~ B,C,D,E,P,UA
'B,C,D,E,P,UA B,C,D,E,P,UA B,C,D,E,'P,UA M,UB M,UB RWCU Suction HV-144F001 HV-144F004 RHR - Reactor Vessel Head S ra HV-151F022 HV"151F 023 30 30 30 20 B,J,M M,UB)Z M,UB,Z SUS(UEHANNA - UNIT 1 3/4 6-19 Amendment No. 23
TABLE 3.6. 3-1 (Continued)
PRIMARY CONTAINMENT ISOLATION VALVES MAXIMUM ISOLATION TIME VALVE FUNCTION AND NUMBER Automatic Isolation Valves (Continued)
Containment Instrument Gas ISOLATION( )
SIGNAL s HV-12603 SV"12605 SV"12651 SV-.12661 SV"12671 RBCCM HV".11313 HV-11314 HV-11345 HV-11346 Containment Pur e
HV-15703
. HV-15704 HV"15705 HV-15711 HV-15713 HV-15714 HV-15721 HV-15722 HV"15723 HV-15724 HV-15725 RHR - Or e'll S ra (f)
HV-151F016 A,B RB Chilled Water HV-18781 Al,A2, Bl, B2 HV-18782 A1,A2,B1,B2 HV-18791 A1,A2, B1, B2 HV-18792 A1,A2, B1, B2 20 N/A N/A N/A N/A 30 30 30 30 19 19 5
5 30 30 6
30 30 19 19 90 40 6
15-4 X
X X.
Y Y
Y,R Y,R Y,R Y,R Y,R Y,R Y,R Y,R Y,R Y,R Y,R SUSQUEHANNA -
UNIT 1 3/4 6"20 enÃssgqL f<o
TABLE 3.6.3-1 (Continued)
PRIMARY CONTAINMENT ISOLATION VALVES MAXIMUM ISOLATION TIME VALVE FUNCTION AND NUMBER
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Automatic Isolation Valves (Continued)
Containment Atmos here Sam le ISOLATION SIGNAL(s)
SV"15734 A, B SV-15736 A, B SV"15737 SV"15740 A,B SV"15742 A,B SV"15750 A, B SV-15752 A,B SV"15767 SV"15774 A,B SV-15776 A,B SV"15780 A,B SV"15782 A,B Reactor Coolant Sam le HV-143F019 HV-143F020 Li uid Radwaste HV"16108 A1, A2 HV-16116 A1, A2 RHR - Su ression Pool I
HV"151F 011 A, B HV-151F028 A,B CS Test(')(')
HV"152F015 A, B HPCI Suction HV-155F042 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 15 15 23 90 60 90 Y
Y Y,R Y
Y Y
Y Y,R Y
Y Y
Y B,C B,C G
SUS(UEHANNA - UNIT 1, I
3/4 6-21 Amendment No.
23
TABLE 3.6.3-1 (Continued)
PRIMARY CONTAINMENT ISOLATION VALVES MAXIMUM ISOLATION TIME VALVE FUNCTION AND NUMBER Automatic Isolation Valves (Continued)
(b)
Su ression Pool Cleanu ISOLATION( )
SIGNAL s)
HV-15766 HV-15768 HPCI Vacuum Breaker HV"155F075 HV-155F079 RCIC Vacuum Breaker HV-149F062 HV-149F084 TIP Bal 1 Valves (g) 5 valves b.
Manual Isolation Valves MSIV-LCS Bleed Valve HV-139F001 B, F, K, P Feedwater(
HV-141F032 A, B RWCU Return HV-144F042 HV-144F104 RCIC In ection HV-149F013 1-49-020 30 30 15 15 10 10 FB FB FA FA SUSQUEHANNA - UNIT 1 3/4 6-22
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TABLE 3.6.3-1 (Continued)
PRIMARY CONTAINMENT ISOLATION VALVES VALVE FUNCTION AND NUMBER Manual Isolation Valves (Continued)
(h)
RCIC Suction HV-149F031 RCIC Turbine Exhaust HV"149F 059 RCIC Vacuum Pum'ischar e
HV-149F060 HPCI In ection HV-155F006(')
1-55-038 RHR - Shutdown Coolin
. Return/
~LPCI 1
HV-151F015 A, 8 RHR - Su ression Pool Suction HV-151F004 A, B, C, 0 RHR Heat Exchan er Vent HV"151F103 A, B HV-152F005 A, B HV-152F037 A,B CS Suction HV-152F001 A, B Containment Instrument Gas SV-12654 A,B SUSQUEHANNA - UNIT 1 3/4 6-23
TABLE 3.6.3-1 (Continue+
PRIMARY CONTAINMENT ISOLATION VALVES VALVE FUNCTION AND NUMBER Manual Isolation Valves (Continued)
(h)
SLC HV-148F006 Breathin Air 1-25-209.
1-25-210 Demineralized Mater 1"41-017 1-41-018 ILRT 1-57-193 1-57-195 HPCI Turbine Exhaust HV-155F066 RHR - Shutdown Cooli n 'eturn/
LPCI In ection - Pressure E ualizin Valve HV-151Fl 22 A,B c.
Other Val ves Feedwater 141F 010', B RHR - Shutdown Coolin Suction PSV-151F126 RHR Shutdown Coolin Return/
HV-151F 050 A, B RHR-Minimum Recirculation Flow HV-151F007 A, B SUS(UEHANNA - UNIT 1 I
3/4 6-24 Amendment No. 23
PLANT SYSTEMS ULTIMATE HEAT SINK LIMITING CONDITION FOR OPERATION 3.7. 1.3 The spray pond shall be OPERABLE.
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, 3, 4, 5 and ".
ACTIDN:
a 4 b.
With the groundwater level at any spray pond area observation well greater than or equal to 663'SL, 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 the next 10 days outlining the cause of the high groundwater level and the plans for restoring the level to within the limit.
With the spray pond otherwise inoperable:
l.
In OPERATIONAL CONDITION 1, 2 or 3, be in at least HOT, SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2.
In OPERATIONAL CONDITION 4 or 5, decl are the RHRSW system and the emergency service wa'ter system inoperable and take the ACTION required by Specifications 3.7. 1. 1 and 3.7. 1.2.
3.
In Operational Condition ", declare the emergency service water system inoperable and take the ACTION required by Specification 3.7. l. 2.
The provisions of Specification 3. O. 3 are not applicable.
SURVEILLANCE RE UIREMENTS 4.7.1.3 The spray pond shall be determined OPERABLE by verifying:
a.
The average water temperature, which shall be the arithmetical average of the spray pond water temperature at the surface, mid and bottom
- levels, to be. less than or equal to 81 F 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.
The water level at the overflow weir is greater than or equal to 6?8'"
mean Sea Level USGS (MSL), at. least once per 'l'2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, c.
The groundwater level at observation wells 1, 3, 4, 5, 6, and 1113 to be less than 663'SL at least once per 31 days.
"When handling irradiated fuel in the secondary containment.
SUSQUEHANNA - UNIT 1 3/4 7-3 Amendment No.
~
PLANT SYSTEMS 3/4.7.2 CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY SYSTEM LIMITING CONDITION FOR OPERATION 3.7.2 Two independent control room emergency outside air supply system subsystems shall be OPERABLE with each subsystem consisting of:
a.
One makeup fan, and b.
One filter train.
APPLICABILITY: All OPERATIONAL CONDITIONS and ~.
ACTION:
a.
In OPERATIONAL CONDITION 1, 2 or 3 with one control room emergency outside air supply subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
In OPERATIONAL CONDITION 4, 5 or ":
1.
With one control room emergency outside air supply subsystem inoperable, restore the inoperable subsystem to OPERABLE st'atus within 7 days or initiate and maintain operation of the OPERABLE subsystem in the pressurization mode of operation.
2.
With both control room emergency outside air supply subsystems inoperable, suspend CORE ALTERATIONS, handling of irradiated fuel in. the'econdary containment and operations with a potential for draining the reactor vessel.
c.
The provisions of Specification 3.0.3 are not applicable in Operational Condition ".
SURVEILLANCE RE UIREMENTS 4.7.2 Each control room emergency outside air supply subsystem shall be demonstrated OPERABLE:
a
~
b.
At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal ads'orber s and verifying that the subsystem operates for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with the heaters OPERABLE.
At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber
- housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the subsystem by:
When irradiated fuel is being handled in the secondary containment, SUS(UEHANNA - UNIT 1 3/4 7-4 Amendment No. 16
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PLANT SYSTEMS 3/4.7.4 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.4 All snubbers listed in Table 3.7.4-l shall be OPERABLE.
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2 and 3 and OPERATIONAL CONDITIONS 4 and 5 for snubbers located on systems required OPERABLE in those OPERATIONAL CONDITIONS.
ACTION:
With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber(s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.4.c on the supported component or declare the supported system inoperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE RE UIREtlENTS 4.7.4 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program arid the requirements of Specification 4 ~ 0.5:
a.
Visual Ins ections The first inservice visual inspection of snubbers shall be performed after 4 months but within 10 months of commencing POWER OPERATION and shall include all snubbers listed in Table 3.7.4-1.
If all snub-bers of each type are found OPERABLE during the first inservice visual inspection, the second inservice visual inspection shall be performed at the first refueling outage.
Otherwise, subsequent visual inspections shall be performed in ac'cordance with the following schedule:
No. Inoperable Snubbers er Ins ecti on Peri od 0
1 2
3,4 5,6,7 8 or more'ubsequent Visual Ins ection Period*8 12 months
+ 25%
6 months
+ 25%
124 days
+ 25%
62 days
+ 25%
31 days
+ 25%
The snubbers may be categorized into two groups:
Those accessible and those inaccessible during reactor operation.
Each group may be inspected independently in accordance with the above schedule.
The inspection interval shall not be lengthened more than one step at a time.
PThe provisions of Specification 4.0.2 are not applicable.
SUS(UEHANNA - UNIT 1 3/4 7-9 Amendment No.
23
PLANT SYSTEMS SURVEILLANCE RE UIREMENTS b.
Visual Ins ection Acce tance Criteria Visual inspections shall verify (1) that there are no visible indications of damage or impaired OPERABILITY, (2) that attachments'o the foundation or supporting structure are secure, and (3) in those locations where snubber movement can be manually induced without disconnecting the snubber, that the snubber has freedom of movement and is not frozen up.
Snubbers which appear inoperable as a result of these visual inspections may be determined OPERABLE for the purpose of establishing the next visual inspection interval, providing that (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers that may be generically susceptible, and (2) the affected snubber is functionally tested in the as found condition and determined OPERABLE per Surveillance Requirements
- 4. 7. 4. d.
Functional Tests During the first refueling shutdown and at.least once per 18 months thereafter during shutdown, a rgpresentative sample of at least that number of snubbers which follows the exp'ression 35 (1 +.~j where c = 4, is the allowable number of snubbers not meeting the acceptance criteria selected by the operator, shall be functionally tested either in-place or in a bench test.
For each number of snubbers above c which does not meet the functional test accept-ance criteria of Specifications 4.7.4.d.,
an additional sample selected according to the expression 35 (1
+ -) (
)
(a - c) shall 2
c + 1 be functionally tested, where a is the total number of snubbers found inoperable during the functional tes.ing of the representative sample.
Functional testing shall continue according to the expression b [35 (l + -) (
) ] where b is the number of snubbers found inoper-c 2
2 2
c+1 able in the previous re-sample, until no additional inoperable snubbers are found within a sample or until all snubbers in Table 3.7.4-1 have been functionally tested.
The representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of snubbers.
At least 25K of the snubbers in the representative sample shall include snubbers from the following three categories:
2.
3.
The first snubber away from each reactor vessel nozzle Each'nubber within 5 feet of heavy equipment,
- valve, ump;
- turbine, motor, etc.
Each snubber within 10 feet of the discharge from a saf ty relief valve.
SUSQUEHANNA - UNIT 1 I
3/4 7"10