ML20215J450
| ML20215J450 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 06/09/1987 |
| From: | Virgilio M Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20215J452 | List: |
| References | |
| NUDOCS 8706250004 | |
| Download: ML20215J450 (17) | |
Text
1
'k UNITED STATES
. [
-g NUCLEAR REGULATORY COMMISSION
- j WASHINGTON, D. C. 20555
\\, % /
i CLEVELAND ELECTRIC ILLUMINATING COMPANY, ET AL.
DOCKET NO. 50-440 PERRY NUCLEAR POWER PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE
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Amendment No. 6 j
License No. NPF-58 l
I 1.
The Nuclear Regulatory Commission (the Commission) has found that:
1 A.
The application for amendment by Cleveland Electric Illuminating Company, Duquesne Light Company, Ohio Edison Company, Pennsylvania Power Company, and Toledo Edison Company (the. licensees) dated.
December 15, 1986, as amended February 10, 1987, complies with the standards and requirements of the Atomic Energy Act of'1954, as amended (the Act), and the Commission's rules and regulations set
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forth in 10 CFR Chapter I; j
8.
The facility will operate in conformity with the application, the l
provisions of the Act, and the rules and 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 i
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-58 is hereby amended to read as follows:
8706250004 B70609 A. LOCK 050 g 0 DR
d 2
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Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 6 are hereby incorporated into this license.
Cleveland Electric Illuminating Company shall operate.the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
g 3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Marti J. Virgilio, Acting Director Project Directorate III-1 Division of Reactor Projects - III, IV, V
& Special Projects
Attachment:
Changes to the Technical Specifications
.j 1
Date of Issuance: June 9,1987
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ATTACHMENT TO LICENSE AMENDMENT NO. 6 FACILITY OPERATING LICENSE N0. NPF-58 DOCKET NO. 50-440 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Overleaf page(s) provided to maintain document completeness.
Remove Insert 1-4 1-4 3/4 5-5 3/4 5-5 3/4 6-21 3/4 6-21 3/4 6-41 3/4 6-41 3/4 8-16 3/4 8-16 3/4 8-24 3/4 8-24 6-15 6-15 e
DEFINITIONS DRYWELL INTEGRITY (continued) f.
The suppression pool is in compliance with the requirements of Specification 3.6.3.1.
g.
The sealing mechanism associated with each drywell penetration; e.g.,
welds, bellows or 0-rings, is OPERABLE.
E-AVERAGE DISINTEGRATION ENERGY 1
1.12 E shall be the average, weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling, of the sum of the average beta and gamma energies per disintegration, in MeV, for isotopes, with half lives greater than 15 minutes, making up at least 95% of the total non-iodine activity in the coolant.
EMERGENCY CORE COOLING SYSTEM (ECCS) RESPONSE TIME d
1.13 The EMERGENCY CORE COOLING SYSTEM (ECCS) RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ECCS actuation setpoint at the channel sensor until the ECCS equipment is capable of performing its safety function, i.e., the valves travel to their required positions, pump dis-charge pressures reach their required values, etc.
Times shall include diesel generator starting and sequence loading delays where applicable.
The response time may be measured by any series of sequential, overlapping or total steps such that the entire response time is measured.
END-0F-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME 1.14 The END-0F-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME shall be that time interval to complete suppression of the electric arc between the fully open contacts of the recirculation pump circuit breaker from initial movement of the associated:
a.
Turbine stop valves, and b.
Turbine control valves.
The response time may be measured by any series of sequential, overlapping or total steps such that the entire response time is measured.
FRACTION OF LIMITING POWER DENSITY 1.15 The FRACTION OF LIMITING POWER DENSITY (FLPD) shall be the LHGR existing at a given location divided by the specified LHGR limit for that bundle type.
FRACTION OF RATED THERMAL POWER 1.16 The FRACTION OF RATED THERMAL POWER (FRiP) shall be the measured THERMAL POWER divided by the RATED THERMAL POWER.
PERRY - UNIT 1 1-3
DEFINITIONS FREQUENCY NOTATION
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1.17 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.
FUEL HANDLING BUILDING INTEGRITY 1.18 FUEL HANDLING BUILDING (FHB) INTEGRITY shall exist when:
j The doors in each access to the 620 foot elevation of the FHB are i
a.
closed, except for normal entry and exit.
I b.
The FHB railroad track door is closed.
The fuel handling area floor hatches are in place.
c.
d.
The FHB ventilation system is in compliance with Specification 3.7.7.1.
The shield blocks are installed adjacent to the Shield Buildingi e.
GASEOUS RADWASTE TREATMENT (OFFGAS) SYSTEM i
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1.19 The GASEOUS RADWASTE TREATMENT (0FFGAS) SYSTEM is the system designed
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and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgasses from the main condenser evacuation system and provid-f ing for delay or holdup for the purpose of reducing the total radioactivity i
prior to release to the environment.
i IDENTIFIED LEAKAGE i
1.20 IDENTIFIED LEAKAGE shall be:
Leakage into collection systems, such as pump seal or valve packing a.
leaks, that is captured and conducted to a sump or collecting tank, or b.
Leakage into the drywell atmosphere from sources that are both specifically located and known either not to interfere with the operation of the leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE.
ISOLATION SYSTEM RESPONSE TIME 1.21 The ISOLATION SYSTEM RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its isolation actuation setpoint'at the channel sensor until the isolation valves travel to their required positions.
Times shall include diesel generator starting and sequence loading delays where applicable.
The response time may be measured by any series of sequential, overlapping or total steps such that the entire response time is I
measured.
l PERRY - UNIT 1 1-4 Amendment No. 6 l
l EMERGENCY CORE COOLING SYSTEMS 1
SURVEILLANCE REQUIREMENTS (Continued) e.
For the ADS by:
1.
At least once per 31 days, performing a CHANNEL FUNCTIONAL TEST of the safety related instrument air system low pressure alarm system.
2.
At least once per 18 months:
a)
Performing a system functional test which includes simulated automatic actuation of the system throughout its emergency operating sequence, but excluding actual valve actuation.
b)
Manually ** opening each ADS valve when the reactor steam dome pressure is greater than or equal to 100 psig* and observing that either:
1)
The control valve or bypass valve position responds accordingly, or 2)
There is a corresponding change in the measured steam flow, or 3)
The safety relief valve discharge pressure switch indicates the valve is open.
c)
Performing a CHANNEL CALIBRATION of the safety related instrument air system 1aw pressure alarm system and verifying an alarm setpoint of > 155 psig with an allowable value of > 151.9 psig on decreasing pressure.
- The provisions of Specification 4.0.4 are not applicable provided the surveillance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure is adequate to perform the test.
PERRY - UNIT 1 3/4 5-5 Amendment No. 6
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EMERGENCY CORE COOLING SYSTEMS j
3/4 5.2 ECCS - SHUTDOWN l
l LIMITING CONDITION FOR OPERATION
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3.5.2 At least two of the following shall be OPERABLE:
I The low pressure core spray (LPCS) system with a flow path cap'ble a.
of taking suction from the suppression pool and transferring the water through the spray sparger to the reactor vessel.
b.
Low pressure coolant injection (LPCI) subsystem "A" of the RHR system with a flow path capable of taking suction from the suppres-sion pool and transferring the water to the reactor vessel.
c.
Low pressure coolant injection (LPCI) subsystem "B" of the RHR system with a flow path capable of taking suction from the suppres-sion pool and transferring the water to the reactor vessel.
d.
Low pressure coolant injection (LPCI) subsystem "C" of the RHR system with a flow path capable of taking suction from the suppres-sion pool and transferring the water to the reactor vessel.
j The high pressure core spray (HPCS) system with a flow path capable j
e.
of taking suction from one of the following water sources and
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transferring the water through the spray sparger to the reactor vessel:
1.
From the suppression pool, or 2 -.
When the suppression pool level is less than the level required by Specification 3.5.3.b, from the condensate storage tank containing at least 150,000 available gallons of water, equivalent to a level of 47% (220,000 gallons of water).
APPLICABILITY:
OPERATIONAL CONDITION 4 and 5*.
l ACTION:
With one of the above required subsystems / systems inoperable, f
a.
restore at least two subsystems / systems to OPERABLE status within l
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or suspend all operations that have a potential for draining the reactor vessel.
j b.
With both of the above required subsystems / systems inoperable, suspend CORE ALTERATIONS and all operations that have a potential for draining the reactor vessel.
Restore at least one subsystem /
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system 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 establish PRIMARY l
CONTAINMENT INTEGRITY within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
With an ECCS discharge line " keep filled" pressure alarm instrumen-c.
tation channel associated with an above required ECCS system inoper-able, perform surveillance 4.5.1.a.1 at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- The ECCS is not required to be OPERABLE provided that the reactor vessel head is removed, the cavity is flooded, the steam dryer storage / reactor well gate is removed, and water level in these upper containment pools is maintained within the limits of Specification 3.9.8 and 3.9.9.
PERRY - UNIT 1 3/4 5-6
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J CONTAINMENT SYSTEMS DRYWELL AVERAGE AIR TEMPERATURE I
LIMITING CONDITION FOR OPERATION
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3.6.2.6 Drywell average air temperature shall not exceed 135 F.
APPLICABILITY: OPERATONAL CONDITIONS 1, 2 and 3.
ACTION:
With the drywell average air temperature greater than 135 F, reduce the average air temperature to within the limit within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-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 /> and in COLD SHUT 00WN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.2.6 The drywell average air temperature shall be the arithmetical average
- of the temperatures at the following elevations # and shall be determined to be within the limit at least once per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:
Elevation Azimuth a.
653'-8" 315, 220, 135, 34 b.
634'-0" - 640'-0" 340, 308, 215, 145,
30, 20 c.
604'-6" - 609'-8" 310, 308, 253, 212,
150, 140, 80
- At least one reading from each elevation for an arithmetical average.
- The temperature at each elevation shall be the arithmetical average of the temperatures obtained from all available instruments at that elevation.
PERRY - UNIT 1 3/4 6-21 Amendment No. 6
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CONTAINMENT SYSTEMS 3/4.6.3 DEPRESSURIZATION SYSTEMS SUPPRESSION POOL LIMITING CONDITION FOR OPERATION 3.6.3.1 The suppression pool shall be OPERABLE with the pool water:
a.
Volume between 115,612 ft3 and 118,548 ft3 equivalent to a level between 18'0" and 18'6", and a b.
Maximum average temperature of 90 F except that the maximum average temperature may be permitted to increase to:
1.
105 F during testing which adds heat to the suppression pool.
2.
110 F with THERMAL POWER less than or equal to 1% of RATED THERMAL POWER.
3.
120 F with the main steam line isolation valves closed following a scram.
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2 and 3.
i ACTION:
With the suppression pool water level outside the above limits, a.
restore the water level to within the limits within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 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 /> 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.
With the suppression pool average water temperature greater than 90 F, restore the average temperature to less than or equal to 90 F j
within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-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 /> 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 />, except, as permitted above:
1.
With the suppression pool average water temperature greater than 105 F during testing which adds heat to the suppress' ion pool, stop all testing which adds heat to the suppression pool and restore the average temperature to less than 90 F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-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 /> 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 />.
2.
With the suppression pool average water temperature greater than:
a) 90 F for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and THERMAL POWER greater than 1% of RATED THERMAL POWER, 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 />.
y l
b) 110 F, place the reactor mode switch in the Shutdown position and operate at least one residual heat removal loop in the suppression pool cooling mode.
l PERRY - UNIT 1 3/4.6-22
SUREVILLANCE REQUIREMENTS 4.6.5.1 Each containment vacuum breaker shall be:
a.
Verified closed 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.
Demonstrated OPERABLE:
1.
At least once per 31 days by:
a)
Cycling the vacuum breaker and isolation valve through at least one complete cycle of full travel b)
Verifying the position indicator OPERABLE by observing expected valve movement during the cycling test.
2.
At least once per 18 months by:
a)
Verifying the pressure differential required to begin to open the vacuum breaker, from the closed position, to be
< 0.1 psid and to be fully open to be < 0.2 psid (out' side containment to containment), and ~
b)
Verifying the position indicator OPERABLE by performance of a CHANNEL CALIBRATION.
3.
By verifying the OPERABILITY of the vacuum breaker isolation valve differential pressure actuation instrumentation with the opening allowable value of > 0.052 psid and < 0.160 psid (containment to out ide containment) by performance of a:
a)
CHANNEL CHECK 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)
CHANNEL FUNCTIONAL TEST at least once per 31 days, and c)
CHANNEL CALIBRATION at least once per 18 months.
PERRY - UNIT 1 3/4 6-41 Amendment No. 6
4 CONTAINMENT HUMIDITY CONTROL LIMITING CONDITION FOR OPERATION 3.6.5.2 Containment average temperature and relative humidity shall be main-tained above the curve shown in Figure 3.6.5.2-1.
APPLICABILITY:
Whenever PRIMARY CONTAINMENT INTEGRITY is required for Specifications 3.6.1.1.1 and 3.6.1.1.2.
ACTION:
With the containment average temperature / relative humidity not within the limits for acceptable operation as shown in Figure 3.6.5.2-1:
In OPERATIONAL CONDITION 1, 2 or 3, restore the average temperature /
a.
relative humidity to within the limits for acceptable operation as shown in Figure 3.6.5.2-1 within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-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 /> 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 />.
i b.
At all other times, either:
1.
Maintain an unobstructed opening (s) in the containment that equals or exceeds the flow area provided by two open vacuum breakers, or 2.
Deactivate the containment spray by closing at least one valve in each containment spray supply header and deenergizing the power supply to its motor operator.
SURVEILLANCE REQUIREMENTS 4.6.5.2 Containment average temperature / relative humidity shall be verified to 1
be within the limits for acceptable operation curve shown in Figure 3.6.5.2-1 at least once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
i t
PERRY - UNIT 1 3/4 6-42
t e
TABLE 4.8.2.1-1 BATTERY SURVEILLANCE' REQUIREMENTS CATEGORY A(1)
CATEGORY B(2)
Parameter Limits for each Limits for each Allowable (3) designated pilot connected cell value for each cell connected cell Electrolyte
> Minimum level
> Minimum level Above top of Level indication mark, indication mark,
- plates, and < " above and < " above and not maxiEum level maxi 5um level overflowing indication mark indication mark-Float Voltage
> 2.13 volts
> 2.13 volts (c)
> 2.07 volts Specifi
> 1.200(b)*
> 1.195(b)*
Not more than Gravity {a)
[1.195(b)*
[1.190(b)**
.020 below the j
average of all-connected cells j
Average of all Average of-all connected cells connected cells-
> 1.205(b)*
> 1.195(b)*.
i1.200(b)**
E1.190(b)
(a). Corrected for electrolyte temperature and. level.
(b) Or battery charging current is less than 2 amperes when on float charge.
(c) -May be corrected for average electrolyte temperature.
(1) For any Category A parameter (s) outside the limit (s) shown, the battery may be considered OPERABLE provided that within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> all the Category B measurements are taken and found to be within their allowable values, and.
provided all Category A and B parameter (s) are restored to within limits within the next 6 days.
(2) For any Category B parameter (s) outside the limit (s) shown, the battery may be considered OPERABLE provided that the Category B parameters are within their allowable values and provided the Category B parameter (s) are restored to within limits within 7 days.
(3) Any Category 'B parameter not within its allowable value indicates an inoperable battery.
- Division 1 and Division 2 battery.
- Division 3 battery.
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PERRY - UNIT 1 3/4 8-15
l 1
ELECTRICAL POWER SYSTEMS-D.C. SOURCES - SHUTDOWN LIMITING CONDITION FOR OPERATION 4
l 3.8.2.2 As a minimum, Division 1 or Division 2, and, when the HPCS system J
t is required to be OPERABLE, Division 3, of the D.C. electrical power sources l
shall be OPERABLE with:
]
a.
Division 1 consisting of:
1.
125 volt battery 1R42-5002 or 2R42-5002.
2.
125 volt full capacity charger 1R42-5006 or OR42-5007.
l b.
Division 2 consisting of:
1.-
125 volt battery 1R42-5003 or 2R42-5003.
2.
125 volt full capacity charger 1R42-5008 or OR42-5009.
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l c.
Division 3 consisting of:
1 1.
125 volt battery 1E22-5005 or 2E22-S005.
]
2, 125 volt full capacity charger 1E22-S006 or OR42-5011.
APPLICABILITY:
OPERATIONAL CONDITIONS 4, 5 and *.
ACTION:
With the Unit 1 and Unit 2 Division 1 batteries and/or both chargers a.
of the above required Division 1 D.C. electrical power sources and the Unit 1 and Unit 2 Division 2 batteries and/or both chargers of the above required Division 2 D.C. electrical power sources inoperable, suspend CORE ALTERATIONS, handling of irradiated fuel in the fuel-handling building or primary containment and operations with a poten-tial for draining the reactor vessel.
b.
With the Unit 1 and Unit 2 Division 3 batteries and/or both chargers of the above required D.C. electrical power sources inoperable, declare the HPCS system inoperable and take the ACTION required by Specification 3.5.2 and 3.5.3.
The provisions of Specification 3.0.3 are not applicable.
c.
SURVEILLANCE REQUIREMENTS 4.8.2.2 Each of the above required battery and charger shall be demonstrated OPERABLE per Surveillance Requirement 4.8.2.1.
- When handling irradiated fuel 'in the Fuel Handling Bul'lding or primary containment.
PERRY - UNIT 1 3/4 8-16 Amendment No. 6
TABLE 3.8.4.1-1 I
CONTAINMENT PENETRATION CONDUCTOR I
OVERCURRENT PROTECTIVE DEVICES 13.8 KV LOAD OVERCURRENT PROTECTION Primary Secondary 1833-C001A L1106 1R22-5012 I
1833-C001B L1205 1R22-5013 120V LOAD OR CIRCUIT 1821-8760XB 1R25-5043-CB20 NA*
l 1821-B756XB 1R25-5043-CB18 NA*
1821-B758XB 1R25-5043-CB19 NA*
1821-B754XB 1R25-SO43-CB17 NA*
l 1B21-B752XB 1R25-5047-CB11 NA*
I 1833-B1X (Sp. Htr.)
1R25-S093-CB7 NA*
1833-83X (Sp. Htr.)
1R25-5093-CB8 NA*
1B33-85X (Sp. Htr.)
1R25-5097-CB5 NA*
1833-B7X (Sp. Htr.)
1R25-S097-CB6 NA*
IB33-B9X (Sp. Htr.)
1R25-SO93-CB9 NA*
IB33-B11X (Sp. Htr.)
1R25-5093-CB10 NA*
1833-B13X (Sp. Htr.)
1R25-5097-CB7 NA*
1833-B15X (Sp. Htr.)
1R25-S097-CB8 NA*
1C11-C1X NA*
1H13-P653-CB1 1C41-B9XB (Sp. Htr) 1R25-5043-CB21 NA*
1E51-B3XB 1R25-5043-CB24 NA*
1E51-B1XB 1R25-S043-CB23 NA*
1F42-B3X (Sp. Htr.)
1R25-5097-CB3 NA*
- Protected by fuse.
PERRY - UNIT 1 3/4 8-23
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TABLE 3.8.4.1-1 (Continued)
_1_20V LOAD OR CIRCUIT OVERCURRENT PROTECTION Primary Secondary 1G41-B1X 1R25-5077-CB1 NA*
1R25-B516X OR25-5054-CB7 NA*
1R25-B517X OR25-5054-CB13 NA*
1R25-8245X 1R25-5057-CB12 NA*
1P56-81060X 1R25-5053-CB34 NA*
IP57-B3XB 1R25-5043-CB15 NA*
q 1R25-B522X OR25-5153-C813 NA*
1R25-B515X 1R25-5053-CB25 NA*
1M16-B7XB 1R25-5047-CB1 NA*
IM16-B9XB 1R25-5047-CB3 NA*
1M16-B17XB 1R25-5047-CBS NA*
1M1C-B19XB 1R25-5047-CB6 NA*
i 1E12-B3XB 1R25-SO47-CB7 NA*
1E12-B7XB 1R25-SO47-CB8 NA*
1E12-B11XB 1R25-5047-CB9 NA*
1E12-B15XB 1R25-5047-CB10 NA*
j 1
- Protected by fuse.
PERRY - UNIT 1 3/4 8-24 Amendment No. 6
ADMINISTRATIVE CONTROLS ACTIVITIES (Continued) n d.
Sections responsible for reviews, including cross-disciplinary re-views, performed in accordance with Specifications 6.5.3.la., and 1
6.5.3.lc., shall be designated in writing by PORC and approved by the i
appropriate Manager, Perry Plant Department.
The individual (s) per-forming the review shall meet or exceed the qualification requirements of appropriate section(s) of ANSI N18.1-1971; Each review shall include a determination pursuant to 10 CFR 50.59 e.
of whether or not the potential for an unreviewed safety question exists.
If such a potential does exist, a safety evaluation per 10 CFR 50.59 to determine whether or not an unreviewed safety question is involved shall be performed.
Pursuant to 10 CFR 50.59, NRC approval of items involving unreviewed safety questions shall be obtained prior to implementation; and l
f.
The Plant Security Plan and Emergency Plan, and implementing instruc-tions, shall be reviewed at least once per 12 months.
Recommended i
changes to the implementing instructions shall be approved by the l
Manager, Perry Plant Technical Department.
Recommended changes to 1
the Plans shall be reviewed pursuant to the requirements of Specifi-cations 6.5.1.6 and 6.5.2.7 and approved by the Manager, Perry Plant Technical Department.
NRC approval shall be obtained as appropriate.
6.6 REPORTABLE EVENT ACTION i
6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
The Commission shall be notified pursuant to the requirements of a.
Section 50.72 to 10 CFR Part 50, and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the PORC and the results-of the review submitted to the SSRC and the Vice President - Nuclear Group.
6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
i The NRC Operations Center shall be notified by telephone as soon as-j a.
possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
The Vice President - Nuclear Group and the NSRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4 b.
A Safety Limit Violation Report shall be prepared.
The report shall I
be reviewed by the PORC.
This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon unit components, systems, or structures, and (3) corrective action taken to_ prevent recurrence, The Safety Limit Violation Report shall be submitted.to the Commission, i
c.
the NSRC, and the Vice President.- Nuclear Group within 30 days of the violation, e
d.
Critical operation of the unit shall not be resumed until authorized
]
by the Commission.
PERRY - UNIT 1 6-15 Amendment No. 6 J
ADMINISTRATIVE CONTROLS 6.8 PROCEDURES / INSTRUCTIONS AND PROGRAMS 6.8.1 Written procedures / instructions shall be established, implemented, and maintained covering the activities referenced below:
The applicable procedures recommended in Appendix A of Regulatory a.
Guide 1.33, Revision 2, February 1978.
b.
The applicable procedures required to implement the requirements of NUREG-0737 and supplements thereto, c.
Security Plan implementation.
d.
Emergency Plan implementation.
e.
PROCESS CONTROL PROGRAM implementation.
i f.
0FFSITE DOSE CALCULATION MANUAL implementation.
g.
Radiological Environmental Monitoring Program implementation, h.
Fire Protection Program implementation.
6.8.2 Each administrative procedure of Specification 6.8.1, and changes
~
thereto, shall be reviewed by the PORC and shall be approved by the Managers, Perry Plant Departments, prior to implementation.
All procedures / instructions shall be reviewed periodically as set forth in administrative procedures.
6.8.3 The following programs shall be established, implemented, and maintained:
i a.
Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels.
The systems include the HPCS, CS, RHR, RCIC, LPCS, feedwater leakage control system, and post-accident sampling systems.
The program shall ir.clude the following:
1.
Preventive maintenance and periodic visual inspection requirements, and 2.
Integrated leak test requirements for each system at refueling cycle intervals or less.
h J
f b.
In-Plant Radiation Monitoring A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under. accident conditions.
This program shall include the following:
1.
Training of personnel, d
2.
Procedures for monitoring, and 3.
Provisions for maintenance of sampling and analysis equipment.
PERRY - UNIT 1 6-16 i
l
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