ML17156A166
| ML17156A166 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 04/23/1985 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17156A167 | List: |
| References | |
| NUDOCS 8504300013 | |
| Download: ML17156A166 (15) | |
Text
~S RjCII~
(4 0
Cy n
r+
~O
+a**+
t UNITEDSTATES
'UCLEAR REGULATORY COMMISSION
,WASHINGTON, D. C. 20555 PENNSYLVANIA POWER Itj LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE, INC.
DOCKET NO. 50-38 EIIE IIEIIANNAETEEECT I TIQN UNIT I AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
41 License No. NPF-14 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The application for an'mendment filed by the Pennsylvania Power
& Light Company, dated November 13, 1984 complies 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.
C.
The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the ComIission;.
There is a.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 Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of 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. 4l
, and the Environmental Protection Plan contained in Appendix B, are hereby ihcorporated in the license.
PP5L shall operate the facility in accordance with the Technical Specifications and the Environmental 'Protection Plan.
SSO430OOSS SSomi PDR ADOCK 05000387I P
PDR This amendment is effective upon start-up following the first refueling outage.
FOR THE NUCLEAR REGULATORY COMMISSION
Enclosure:
Changes to the Technical Specifications Date of Issuance:
APR 3 3 $%
A. Schwencer, Chief Licensing Branch No.
2 Division of Licensing
ATTACHMENT TO LICENSE AMENDMENT NO.
41 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 3-3 3/4 3-4 3/4 3-5 3/4 3-6 3/4 3-7 3/4 3-8 3/4 3-51 3/4 3-52 3/4 8-33 3/4 8-34 INSERT 2~3 2-4 3/4 3-3 3/4 3-4 3/4 3-5 3/4 3-6 3/4 3-7 3/4 3-8 3/4 3-51 3/4 3-52 3/4 8-33 3/4 8-34
SAFETY LIMITS AND LIMI NG 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:
Mith a reactor 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
TABLE 2.2.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS 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.
4.
d.
Inoperative 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 a.
Level Transmitter b.
Float Switch 9.
Turbine Stop Valve - Closure 10.
Turbine Control Valve Fast Closure, Trip Oil Pressure
- Low ll.
Reactor Mode Switch Shutdown Position 12.
Manual Scram See Bases Figure B 3/4 3-1.
FUNCTIONAL UNIT l.
Intermediate Range. Monitor, Neutron Flux-High TRIP SETPOINT
< 120/125 divisions of full scale
< 15X 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"
< 10X closed
< 3.0 x full power
Background
< 1.72 psig
< 88 gallons
< 88 gallons
< 5 5X closed
> 500 psig NA ALLOWABLE VALUES
< 122/125 divisions of full scale I
< 20X of RATED THERMAL POWER
< 0.58 W+62X, with a maximum of
< 115.5X of RATED THERMAL POWER
< 120X of RATED 7HERMAL POWER NA
< 1057 psig
. > 11.5 inches above instrument zero
< 11X closed
< 3.6 x full power background
< 1.88 psig
< 88 gallons
< 88 gallons
< 7X closed
> 460 psig NA NA
TABLE 3.3. 1-1 (Continued)
REACTOR PROTECTION SYSTEM INSTRUMENTATION FUNCTIONAL UNIT 7.
Drywell Pressure - High 8.
Scram Discharge Volume Mater Level - High a.
Level Transmitter b.
Float Switch 9.
Turbine Stop Valve - Closure APPLICABLE OPERATIONAL CONDITIONS 2(h) ly 2(i) r 5
1% 2(
~ )
5 1(i)
MINIMUM OPERABLE CHANNELS PER TRIP'SYSTEM'{a 2
2 2
2 4(k)
ACTION 1
3 1
3 10.
Turbine Control Valve Fast Closure, Valve Trip System Oil Pressure - Low 1
~
2(k) 11.
Reactor Mode Switch Shutdown Position 12.
Manual Scram 1,
2 3, 4 5
1, 2
3, 4 5
1 1
1 2
2 2
1 7
3 1
8 9
TABLE 3.3.1-1 (Continued)
REACTOR PROTECTION SYSTEM INSTRUMENTATION ACTION STATEMENTS ACTION 1
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 />.
ACTION 2 ACTION 3 ACTION 4
- ACTION 5 ACTION 6 Verify all insertable control rods to be inserted in the core and lock the reactor mode switch in the Shutdown position within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
Suspend all operations involving CORE ALTERATIONS and insert all insertable control rods within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
Be in at least STARTUP within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
Be in STARTUP with the main steam line isolation valves closed within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or 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 />.
Initiate a reduction in THERMAL POWER within 15 minutes and reduce turbine first stage pressure until the function is automatically bypassed within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
I
)
ACTION 7 ACTION 8 "-
ACTION 9 Verify a11 insertable controi rods to be inserted within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.P'l Lock the reactor mode switch in the Shutdown position within I
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
Suspend all operations involving CORE ALTERATIONS, and insert all insertable control rods and lock the reactor. mode switch in the SHUTDOWN position within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
SUS(UEHANNA " UNIT 1 3/4 3"4 Amendment No. 36
TABLE 3.3.1-1 (Continued)
REACTOR PROTECTION SYSTEM INSTRUMENTATION TABLE NOTATIONS (a)
A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillan'ce without placing the trip system in the tripped condition provided at least one OPERABLE channel in the same trip system is monitoring that parameter.
(b)
This function is automatically bypassed when the reactor mode switch is in the Run position.
(c)
The "shorting links" shall be removed from the RPS circuitry prior to and during the time any control rod is withdrawn" and shutdown margin demonstrations performed per Specification
- 3. 10. 3.
(d)
The non-coincident NMS reactor trip function logic is such that all channels go to both trip systems.
Therefore, when the "shorting links" are
- removed, the Minimum OPERABLE Channels Per Trip System is 4 APRMS and 6 IRMS.
(e)
An APRM channel is inoperable if there are less than 2
LPRM inputs per level or less than 14 LPRM inputs to an APRM channel.
(f)
This function is not required to be OPERABLE when the reactor pressure vessel head is unbolted or removed per Specification
- 3. 10. 1;
,(g)
This. function is automatically bypassed when the reactor mode switch is not in the Run position.
(h)
This function is not required to be OPERABLE when PRIMARY CONTAINMENT INTEGRITY is not required.
(i)
With any control rod withdrawn.
Not applicable to control rods removed per Specification 3. 9. 10. 1 or 3. 9. 10. 2.
(j)
This function shall be automatically bypassed when turbine first. stage pressure is less than 108 psig or 17K of the value of first stage pressure.
in psia at valves wide open (V.W. 0) steam flow, equivalent to THERMAL POWER of about 24K of RATED THERMAL POWER.
(k)
Also actuates the EOC-RPT system.
Not requ) red for control rods removed per Specification
- 3. 9. 10. 1 or 3. 9.10. 2:
SUS(UEHANNA " UNIT 1 3/4 3"5 Amendment No.'L9
TABLE 3.3.1-2 REACTOR PROTECTION SYSTEM RESRONSE TIMES FUNCTIONAL UNIT
RESPONSE
TIME (Seconds 1..
a.
Neutron Flux - High b.
Inoperative 2.
Average Power Range Monitor*:
~ a.
Neutron Flux - Upscale, Setdown b.
'low Biased Simulated Thermal Power - Upscale c.
Fixed Neutron Flux - Upscale d.
Inoperative 3.
Reactor Vessel Steam Dome Pressure - High 4.
- Reactor Vessel Water Level - Low, Level 3
5.
Main Steam Line Isolation Valve - Closure 6.
Main Steam Line Radiation - High 7.
Orwell Pressure High 8.
Scram Discharge Volume Water Level - High a.
Level Transmitter
~
b.
Float Switch NA NA NA 0 09**
< 0.09 HA
< 0.55
< 1.05
< 0.06 NA NA NA NA 9.
Turbine Stop Valve - Closure 10.
Turbine Control Valve Fast Closure, Trip Oil Pressure Low ll.
Reactor Mode Switch Shutdown Position 12.
< 0.06
< 0.08¹ HA NA eutron detectors are exempt from response time testing.
Response
time shal'I be measured from the detector output or from the input of the first electronic component in the channel.
""Not including simulated thermal power time constant.
¹Measured from actuation of fast-acting solenoid.
TABLE 4.3.1.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS
~
~
b.
Inoperative FUNCTIONAL UNIT 1;
a.
Neutron Flux - High CHANNEL CHECK S/U,S, S/U W
S NA S/u('),W 234, 5 I
E',3,4,H SA SA CHANNEL OPERATIONAL FUNCTIONAL CHANNEL ( )
CONDITIONS FOR WHICH TEST CALIBRATION SURVEILLANCE RE UIRED 2.
Average Power Range Monitor(f).
a.
Neutron Flux-S/U,s,
- Upscale, Setdown S
b.
Flow Biased Simulated Thermal Power - Upscale S,
D S/U '),
W W
s/U('),
w SA SA 2
3, 5 c.
Fixed Neutron Flux-Upscale d.
Inoperative 3.
Reactor Vessel Steam Dome Pressure - High 4.
Reactor Vessel Water Level-Low, Level.3 5.
Main Steam Line Isolation Valve - Closure 6.
Main Steam Line Radiation-High 7.
Drywell Pressure-High NA S
S/u('),
W S/U(')W W('), SA.
1,2,3,5 1, 2 1, 2 2(i) 1, 2
CA AD I
FUNCTIONAL UNIT CHANNEL CHECK CHANNEL OPERATIONAL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH TEST CALIBRATION SURVEILLANCE RE UIRED TABLE 4.3.1.1-1 (Continued)
REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS C
M O
NA NA NA 1,2,3,4,5 1,2,3,4,5 8.
Scram Discharge Volume Water Level - High a.
Level Transmitter M.
R 1;2,5j b.
Float Switch M
R 1,2,5 9.
Turbine Stop Valve - Closure M
R
'0.
Turbine Control Valve Fast Closure Valve Trip System Oil Pressure
- Low NA M
R 1
ll.
Reactor Mode Switch Shutdown Position NA R
NA 12.
Manual Scram NA M
NA N I I.
Y A I
A A I CIIAIINNL CALIBRATION.
(b)
The IRM and SRM channels shall be determined to overlap for at least 0.5 decades during each startup after entering OPERATIONAL CONDITION 2 and the IRM and APRM channels shall be determined to overlap for at least 0.5 decades during each controlled shutdown, if not performed within the previous 7 days.
(c)
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to startup, i.f not performed within the previous 7 days.
(d)
This calibration shall consist of the adjustment of the APRM channel to conform to the power values calculated by a heat balance during OPERATIONAL CONDITION 1 when THERMAL POWER > 25X of RATED THERMAL POWER.
Adjust the APRM channel if the absolute difference is greater tKan 2X of RATED THERMAL POWER.
Any APRM channel gain adjustment made in compliance with Specification 3.2.2 shall not be included in determining the absolute difference.
(e)
This calibration shall consist of the adjustment of the APRM flow biased channel to conform to a calibrated flow signal.
(f)
The LPRMs shall be calibrated at least once per 1000 effective ful'l.power hours (EFPH) using the TIP system.
(g)
Verify measured core flow to be greater than or equal to established core flow at the existing loop flow.
(h)
This calibration shall consist of verifying the 6 + 1 second simulated thermal power time constant.
(i)
This function is not required to be OPERABLE when the reactor pressure vessel head.is unbolted or removed per Specification 3. 10. 1.
(j)
With any control rod withdrawn.
Not applicable to control rods removed per Specification 3.9.10.1 or 3.9. 10.2.
'l INSTRUMENTATION ~
3/4.3.6 CONTROL ROD BLOCK INSTRUMENTATION LIMITING CONDITION FOR OPERATION
'"3.3.6.
The control rod"'block instrumentation channels shown in Table 3.3.6-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table.3.3.6-2.
APPLICABILITY: As shown in Table 3.3.6-1.
ACTION:
a.
With a control rod block instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.6-2, declare the channel inoperable until the channel is restored to OPERABLE status'with its trip setpoint adjusted consistent with the Trip Setpoint'value.
b.
With the number of OPERABLE channels less than required by the Minimum OPERABt.E Channels per Trip Function requirement, take the ACTION required by Table 3.3.6-1.
SURVEILLANCE RE UIREMENTS 4.3.6.
Each of the-above required control rod block trip systems and instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in.Table 4.3.6-1.
SUS(UEHANNA - UNIT 1 3/4 3"51
TRIP FUNCTION 1.
ROD BLOCK MONITOR TABLE 3.3.6-1 CONTROL ROD BLOCK INSTRUMENTATION MINIMUM APPLICABLE OPERABLE CHANNELS I
OPERATIONAL PER TRIP FUNCTION CONDITIONS ACTION M
W I
~
Ql PO O
a.
Upscale b.
Inoperative c.
Downscale 2.
APRM a.
Flow Biased Neutron Flux-Upscale b.
Inoperative c.
Downscale d.
Neutron Flux - Upscale, Startup 3.
SOURCE RANGE MONITORS a.
Detector not full in b.
Upscale~
~
c.
Inoperative d.
Downscale 4.
INTERMEDIATE RANGE MONITORS a.
Detector not full in b.
Upscale c.
Inoperative>
d.
Downscale 5.
Water Level-High 6.
REACTOR COOLANT SYSTEM RECIRCULATION FLOW a.
Upscale b.
Inoperative c.
Comparator
]A 1'4 1 III 1
1, 1
2 $
'2 5
2 5
2 5'2 5
2 2 $
2 2
2, 5
5 5
5 55-5*III 60 60 60 61 61 61 61 61 61 61 61
. 61 61 61 61 61 61 61 61 62 62 62 62
ELECTRICAL POWER SYSTEMS REACTOR PROTECTION SYSTEM ELECTRIC POWER MONITORING
'LIMITING CONDITION FOR-OPERATION 3.8.4.3 Two RPS electric power monitoring assemblies for each inservice RPS MG set or alternate 'power supply shall. be OPERABLE.
APPLICABILITY: At 'a'l l times.
ACTION:
a.
With one RPS electric power monitoring assembly for an inservice RPS MG set or alternate power supply inoperable, restore the inoperable power monitoring assembly to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or remove the associated RPS MG set or alternate power supply from service.
b.
With both RPS electric power monitoring assemblies for an inservice RPS MG set or alternate power supply inoperable, restore at least one electric power monitoring assembly to OPERABLE status within 30 minutes or remove the associated RPS MG set or alternate power supply from service.
SURVEILLANCE RE UIREMENTS 4.8.4.3 The above specified RPS electric power monitoring assemblies shall, be determined OPERABLE:
a.
By performance of a CHANNEL FUNCTIONAL TEST each time the plant is in COLO SHUTDOWN for a period of more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,.unless performed within the previous 6 months.
b.
At least once per 18 months by demonstrating the OPERABILITY of overvoltage, undervoltage and underfrequency protective instrumentation by performance of a CHANNEL CALIBRATION including simulated automatic actuation of the protective relays, tripping logic and output circuit breakers and verifying the following setpoints:
RPS Division A RPS Division B l.
Overvoltage 2.
Undervoltage 3.
Underfrequency
< 128.3 VAC
> 110.7 VAC"*
> 57 Hz
< 129.5 VAC
> 111.9 VAC""
> 57 Hz
"*Initial setpoint.
Final setpoint to be determined during startup testing following the first refueling outage.
- Any required change to this setpoint shall be submitted to the Commission within 90 days of test completion.
SUS(UEHANNA - UNIT 1 3/4 8-33 Amendment No. 41
l