ML17156A160
| ML17156A160 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 04/23/1985 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17156A162 | List: |
| References | |
| NUDOCS 8504300007 | |
| Download: ML17156A160 (10) | |
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UNITEDSTATES NUCLEAR REGULATORY COMMtSSION WASHINGTON, D. C. 20555 PENNSYLVANIA POWER 8t LIGHT COMPANY ALLEGHENY ELECTRIC CO PERATIVE INC.
DOCKET N
. 50-387 SUE UEIIAMNA S~TEAM E <<T IS ST TIIIM UNIT I AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
4p License No. NPF-14 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The application for an amendment filed by the Pennsylvania Power 8 Light Company, dated October 31, 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.
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 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 iII Appendix A, as revised through Amendment No.
4p, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
PP8L shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
8504300007 850428 PDR ADOCK 05000387 P
I 1
t l
3.
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:
AP"
~ 8 A. Schwencer, Chief Licensing Branch No.
2 Division of Licensing
ATTACHMENT TO LICENSE AMENDMENT NO.
40 FACILITY OPERATING LICENSE NO. NPF-14 DOCKET NO. 50-387 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 3/4 3-7]'/43-72 3/4 3-73 3/4 3-74 3/4 6-27 3/4 6-28 INSERT 3/4 3-71 3/4 3-72 3/4 3-73 3/4 3-74 3/4 6-27 3/4 6-28
Vl CA AD m
INSTRUMENT TABLE 3.3.7.5-1 ACCIDENT MONITORING INSTRUMENTATION MINIMUM
< REQUIRED NUMBER CHANNELS OF CHANNELS OPERABLE 2
2 8,
6 locations 2
2/range 2
-2 2
1/valve" 2
1 6, 1/location 1
- 1/range 1
1 1
1/valve" 1
1.
Reactor Vessel Steam Domy Pressure 2.
Reactor Vessel Mater Level 3:
Suppression Chamber Mater Level 4.
Suppression Chamber Mater Temperature 5.
Suppression Chamber Air Temperature 6.
Primary Containment Pressure 7.
Drywell Temperature 8.
Drywell Gaseous Analyzer a.
Oxygen b.
Hydrogen 9.
Safety/Relief Valve Position Indicators 10.
Containment High Radiation ll.
Noble gas monitors""
a.
Reactor Bldg. Vent b.
SGTS Vent c.
Turbine Bldg. Vent 12.
Neutron Flux ACTION 80 80 80 80 80 80 80 80 82 80 81 81 81 81 80 APPLICABLE OPERATIONAL CONDITION 1
2
~
tip 2 1
2 1:2 1,
2 1
2 1
2 1¹, 2¹ 1¹, 2¹ 1
2 1,
2 1,
2 and ""*
1, 2 and "**
1 2
1 2
O C)
"Acoustic monitor.
""Hid-range and high-range channels
- ""Mhen moving irradiated fuel in the secondary containment.
¹See Special Test Exception 3;10.1
ACTION 80-TABLE 3.3.7.5-1 (Continued)
ACCIDENT MONITORING INSTRUMENTATION ACTION STATEMENT a.
With the number of OPERABLE accident monitoring instrumentation channels less than the Required Number of Channels shown in Table.--
3.3.7.5-1; restore the inoperable channel(s) 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 />.
b.
With the number of OPERABLE accident monitoring instrumentation channels less than the Minimum Channels OPERABLE requirements of Table 3.3.7.5-1, restore the inoperable channel(s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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 />.
ACTION 81 With the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirement, initiate the preplanned alternate method of monitoring the appropriate parameter(s) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />;. and:
ACTION 82 2.
either restore the inoperable channel(s) to OPERABLE status within 7 days of the event, or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days following the event outlining the action taken, the cause of the inoperability, and the plans and schedule for restoring the system to OPERABLE
~ status.
a.
With the number of OPERABLE channels one less than the required Number of Channels shown in Table 3.3.7.5-1, restore the inoper-able channel to OPERABLE-status within 30 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 />.
b.
With the number of OPERABLE channels less than the Minimum Channels OPERABLE requirements of Table 3.3;7.5-1, restore at least one channel 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 />.
SUS(UEHANNA - UNIT 1 3/4 3-72 Amendment No. 36
TABLE 4,3.7.5-1 I
ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREHENTS C:
INSTRUMENT'.
Reactor Vessel Steam Dome Pressure
+
2.
Suppression Chamber Water Level 4.
Suppression Chamber Water Temperature 5.
Suppression Chamber Air Temperature 6.
Primary Containment Pressure 7.
Drywell Temperature 8.
Drywell Oxygen/Hydrogen Analyzer 9.
Safety/Relief Valve Position Indicators 10.
Containment High Radiation ll.
Noble gas monitors a.
Reactor Bldg. Vent b.
SGTS Vent c.
Turbine Bldg. Vent 12.
Neutron Flux CMANNEL CHECK H
H M
H M
H H
H H
H CHANNEL CALIBRATION R
R R
R i
R R
.or hydrogen ana yzer, use sampl.e gas containing:
a.
Nominal zero volume percent
b.
Nominal thirty volume percent
- "CHANNEL CALIBRATION shall consist of an electronic calibration of the channel, not including the detector, for range decades above 10 R/hr and a one point calibration check of the detector below 10 R/hr with an installed or portable gamma source.
D CD
INSTRUMENTATION SOURCE RANGE MONITORS
.LIMITING CONDITION FOR OPERATION 3.3.7.6 At least three source range monitor channels shall be OPERABLE.
APPLICABILITY:
OPERATIONAL CONDITIONS 2",
3 and 4.
ACTION:
In OPERATIONAL CONDITION 2" with one of the above required source range monitor channels inoperable, restore at least 3 source range monitor channels to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 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 />.
b.
In OPERATIONAL CONDITION 3 or 4 with two or more of the above required source range monitor channels inoperable, verify all insertable control rods to be inserted in the core and lock the reactor mode switch in i2$
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 />.
SURVEILLANCE RE UIREMENTS 4.3.7.6 Each of the, above required source range monitor channel.s shall be demonstrated OPERABLE by:
a.
'erformance of a:
1.
CHANNEL CHECK at least once per:
X a) 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in CONDITION 2", and b) 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in CONDITION 3 or 4.
2.-
CHANNEL CALIBRATION""at least once per 18 months.
b.
Performance of a CHANNEL FUNCTIONAL TEST:
1.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to moving the reactor mode switch from the Shutdown position, if not performed within the previous 7 days, and 2.
At least once per 31 days.
c.
Verifying, prior to withdrawal of control rods, that the SRM count rate is at least 0.7 cps""" with the detector fully inserted.
"Mith IRM's on range 2 or below.
""Neutron detectors may be excluded from CHANNEL CALIBRATION.
"""Provided signal-to-noise ratio is
> 2, otherwise
- 3. cps.
SUSQUEHANNA " UNIT 1 3/4 3-74 Amendment No. 36
TABLE 3. 6. 3-1 (Continued)'RIMARY CONTAINMENT ISOLATION VALVES VALVE FUNCTION AND NUMBER Excess Flow Check Valves (Continued)
Reactor Recirculation XV-143F003 A,.B-XV"143F004 A,B XV-143F009 A,B,C,D XV"143F010 A,B,C,D XV-143F011 A,B,C,D XV-143F012 A,B,C,D XV-143F040 A,B, C, D XV-143F057 A,B Nuclear Boiler Vessel Instrument XV-142F041 XV-142F043 A,B XV-142F045 A,B XV-142F047 A,B XV-142F051 A,B,C,D XV"142F053 A,B,C,D XV-142F055 XV"142F057 XV-142F059 A,B,C,D,E,F,G,H,L,M,N,P,R,S,T,U XV-142F061 XV-14201 XV-14202 Nuclear Boiler XV-141F070 A,B,C,D XV-141F071 A,B,C,D'V-141F072A,B,C,D XV-141F073 A,B,C,D XV-141F009 MSIVLCS XV-13910 B,F,K,P SUSQUEHANNA - UNIT 1 3/4 6-27 Amendment No.
40
TABLE 3.6.3-1 (Continued)
PRIMARY CONTAINMENT ISOLATION VALVES A
ON (a)
See Specification 3.3,.2, Table 3.3.2-1, for isolation signal(s) that operates each automatic isolation valve.
All power operated isolation. valves may be opened or closed remote-manually.
(b) Isolation barrier remains water filled or a -'water seal remains in the line post-LOCA.
Isolation valve is, tested with water.
Isolation valve leakage is not included in 0.60 La total Type B and C tests.
(c) Redundant isolation boundary for this valve is provided by the closed system whose integrity is verified by Type A test.
(d) Automatic isolation signal causes TIP to retract; ball valve closes when probe is fully retracted.
(e)- Power assisted check valve.
SUS(UEHANNA " UNIT 1 3/4 6"28 Amendment No. 36