ML20072S590
| ML20072S590 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 09/02/1994 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20072S593 | List: |
| References | |
| NUDOCS 9409140142 | |
| Download: ML20072S590 (14) | |
Text
-..
+'"
- ('D,1f*(' S E
UNITED STATES i
NUCLEAR REGULATORY COMMISSION k..v
/
WASHINGTON, D.C. 20555-0001 PACIFIC GAS AND ELECTRIC COMPANY DOCKET NO. 50-275 DIABLO CANYON NUCLEAR POWER PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 94 License No. DPR-80 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Pacific Gas & Electric Company (the licensee) dated May 7, 1993, complies with the standards and l
requirements of the Atomic Energy Act of 1954, as amended (the l
Act), and the Commission's regulations set forth in 10 CFR Chapter I;
t l
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the i
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; i
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. DPR-80 is hereby amended to read as follows:
l l
9409140142 940902 PDR ADOCK 05000275 p
l
~
}..
i l'
(2)
Technical Soecifications The Technical Specifications contained in Appendix A and the i
Environmental Protection Plan contained in Appendix B, as revised i
i through Amendment No.
94, are hereby incorporated in the j
license.
Pacific Gas & Electric Company shall operate the facility in accordance with the Technical Specifications and the j
Environmental Protection Plan, except where otherwise stated 'in.
l specific license conditions.
3.
This license amendment is effective within 30 days from the date of its issuance.
J FOR THE NUCLEAR REGULATORY COMMISSION 5
pW L
fzr4 The[oreR.
ua, Director-Pr6 ject Directorate IV Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 2, 1994 i
l
poscyA 5
E UNITED STATES 5
NUCLEAR REGULATORY COMMISSION t
e#
WASHINGTON, D.C. 20555-4001 g
j PACIFIC GAS AND ELECTRIC COMPANY DOCKET NO. 50-323 DIABLO CANYON NUCLEAR POWER PLANT. UNIT N0. 2 l
AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No. 93 l
License No. DPR-82 i
1.
The Nuclear Regulatory Commission (the Commission)-has found that:
A.
The application for amendment by Pacific Gas &-Electric Company.
(the licensee) dated May 7,1993, 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 l
I; B.
The facility will operate in conformity with the application, the 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 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 i
E.
The issuance of this amendment is in accordance with 10 CFR Part l
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. DPR-82 is hereby amended to read as follows:
i
. (2)
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.
93, are hereby incorporated in the license.
Pacific Gas & Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions.
3.
This license amendment is effective within 30 days from the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 194 l
Theodore R. Q y, Director Project Directorate IV-2 l
Division of Reactor Projects III/IV l
Office of Nuclear Reactor Regulation
Attachment:
l Changes-to the Technical Specifications Date of Issuance: September 2, 1994 l
l l
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 94 TO FACILITY OPERATING LICENSE NO. DPR-80 AND AMENDMENT NO. 93 TO FACILITY OPERATING LICENSE NO. DPR-82 DOCKET NOS. 50-275 AND 50-323 Revise Appendix A Technical Specifications by removing the pages' identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area l
of change. Overleaf pages are also included, as appropriate.
REMOVE INSERT i
vi vi
(
3/4 3-47 3/4 3-47 3/4 3-48 3/4 3-48 3/4 3-49 3/4 3 B 3/4 3-3 8 3/4 3-3 l'
B 3/4 3-3a B 3/4 3-3b B 3/4 3-3c B 3/4 3-3d l
l l
l
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS SECTION P.AQ1 3/4.3 INSTRUMENTATION (continued)
TABLE 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETP0INTS.........................
3/4 3-23 TABLE 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES..............
3/4 3-28 TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS..............
3/4 3-32 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring for Plant Operations..............
3/4 3-36 TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS............................................
3/4 3-37 TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS SURVEILLANCE REQUIREMENTS...................
3/4 3-39 Movabl e Incore Detectors...............................
3/4 3-40 Seismic Instrumentation................................
3/4 3-41 TABLE 3.3-7 SEISMIC HONITORING INSTRUMENTATION.....................
3/4 3-42 TABLE 4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS..............................
3/4 3-43 Meteorological Instrumentation.........................
3/4 3-44 TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION..............
3/4 3-45 TABLE 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS...........................................
3/4 3-46 Remote Shutdown Instrumentation and Controls...........
3/4 3-47 TABLE 3.3-9 REMOTE SHUTDOWN MONITORING INSTRUMENTATION AND CONTR0LS...............................................
3/4 3-48 TABLE 4.3-6 REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS..............................
3/4 3-49 Accident Monitoring Instrumentation....................
3/4 3-50 TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION....................
3/4 3-52 TABLE 4.3-7 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS..............................
3/4 3-53 l
l l
DIABLO CANYON - UNITS I & 2 vi Amendment Nos. 94 and 93
INSTRUMENTATION i.
REMOTE SHUTDOWN INSTRUMENTATION AND CONTROLS t
LIMITING CONDITION FOR OPERATION I
i 3.3.3.5 The remote shutdown monitoring instrumentation and control functions shown in Table 3.3-9 shall be OPERABLE.
APPLICABILITY: MODES 1, 2 and 3.
ACTION:
a.
With less than the minimum required Function (s) of Table 3.3-9 operable, restore the inoperable Function (s) to OPERABLE status within 30 days or be in 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.
The provisions of Specification 3.0.4 are not applicable, c.
Separate entry into Action a. is allowed for each Function in Table 3.3-9.
SURVEILLANCE RE0UIREMENTS 4.3.3.5.1 Each remote shutdown monitoring instrumentation channel shall be l-demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION at the frequencies shown in Table 4.3-6.
4.3.3.5.2 Verify each required control circuit and control transfer switch is capable of performing the intended function at least once every 18 months.
1 DIABLO CANYON - UNITS 1 & 2 3/4 3-47 Amendment Nos. 94 and 93
)
e TABLE 3.3-9 REMOTE SHUTDOWN MONITORING INSTRUMENTATION AND CONTROLS REQUIRED READOUT / CONTROL NUMBER OF INSTRUMENT / CONTROL FUNCTISH LOCATION CHANNELS 1.
Reactor Trip Breaker Indication Reactor Trip Breaker 1/ trip breaker 2.
Pressurizer Pressure Hot Shutdown Panel 1
3.
Pressurizer Level Hot Shutdown Panel 1
4.
Steam Generator Pressure Hot Shutdown Panel 1/stm. gen.
5.
Steam Generator Wide Range Water Hot Shutdown Panel 1/stm. gen.
Level 6.
Condensate Storage Tank Water Hot Shutdown Panel 1
Level 7.
Auxiliary Feedwater Flow Hot Shutdown Panel 1/stm. gen, i
i 8.
Charging Flow Hot Shutdown Panel 1
9.
RCS Loop 1 Temperature Dedicated Shutdown Hot and Cold Leg Indication Panel Temperature l
Indication
- 10. Auxiliary Feedwater Flow l
Control l
- AFW Pump, and Associated Valves Hot Shutdown Panel any 2 of 3 AFW
- Transfer Switches 4 kV Switchgear pumps 11.
Charging Flow Control
- Centrifugal Charging Pump Hot Shutdown Panel 2 of 2 pumps
- Transfer Switch 4 kV Switchgear l
i 12.
Component Cooling Water Control
- Component Cooling Water Pump Hot Shutdown Panel any 2 of 3 CCW
- Transfer Switch 4 kV Switchgear pumps l
- 13. Auxiliary Saltwater control
- Auxiliary Saltwater Pump Hot Shutdown Panel 2 of 2 pumps
- Transfer Switch 4 kV Switchgear 14.
Emergency Diesel Generator Control
- EDG Start EDG Local Control Panel 3 of 3 EDGs DIABLO CANYON - UNITS 1 & 2 3/4 3-48 Amendment Nos. 94 and 93 l
i..
TABLE 4.3-6 REMOTE SHUTDOWN MONITORING INSTRUMENTATION l
SURVEILLANCE RE0VIREMENTS I
CHANNEL -
CHANNEL INSTRUMENT CHECK CALIBRATION 1.
Reactor Trip Breaker Indication N.A.
N.A.
2.
Pressurizer Pressure M
R 3.
Pressurizer Level M
R 4.
Steam Generator Wide Range Water Level M
R 5.
Steam Generator Pressure M
R 6.
Condensate Storage Tank Water Level M
R 7.
Auxiliary Feedwater Flow M
R l
l 8.
Charging Flow M
R 9.
RCS Loop 1 Temperature Indication M
R DIABLO CANYON - UNITS 1 & 2 3/4 3-49 Amendment Nos. 94 and 93
l l-e INSTRUMENTATION BASES f
3/4.3.3.3 SEISMIC INSTRUMENTATION l
The OPERABILITY of the seismic instrumentation ensu'res that sufficient capability is available to promptly determine the magnitude of a seismic event 4
and evaluate the response of those features important to safety. This 1
capability is required to permit comparison of the measured response to that used in the design basis for the facility to determine if plant shutdown is required pursuant to Appendix A of 10 CFR Part 100. The instrumentation is consistent with the reconnendations of Regulatory Guide 1.12, " Instrumentation for Earthquakes."
3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioac-tive materials to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with the recommendations of Regulatory Guide 1.23, "Onsite Meteorological Programs," February 1972.
3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION BACKGROUND The Remote Shutdown Instrumentation and Controls provide the control room operator with sufficient instrumentation and controls to place and maintain the unit in a safe shutdown condition from a location other than the control room.
This capability is necessary to protect against the possibility that the control room becomes inaccessible. A safe shutdown condition is defined as MODE 3.
With the unit in MODE 3, the Auxiliary feedwater (AFW)
System and the steam generator (SG) safety valves can be used to remove core decay heat and meet all safety requirements. The long term supply of water for the AFW System allows extended operation in MODE 3 from outside the control room until such a time that either control is transferred back to the control room or a cooldown is initiated.
In the event that the control room becomes inaccessible, the operators can establish control at the remote shutdown panel (hot shutdown panel), and place and maintain the unit in MODE 3.
Not all controls and necessary transfer switches are located at the hot shutdown panel. Some controls and transfer switches will have to be operated locally at the switchgear, motor control panels, or other local stations. The unit automatically reaches MODE 3 following a unit shutdown and can be maintained safely in MODE 3 for an extended period of time.
The OPERABILITY of the remote shutdown control and instrumentation functions ensures there is sufficient information available on selected unit parameters to place and maintain the unit in MODE 3 should the control room become inaccessible.
DIABLO CANYON - UNITS 1 & 2 B 3/4 3-3 Amendment Nos. 94 and 93
(
l INSTRUMENTATION f'.
i BASES 3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION (Continued)
APPLICABLE SAFETY ANALYSES 1
i The Remote Shutdown Instrumentation and Controls provides equipment at appropriate locations outside the control room with a capability to promptly shut down and maintain the unit in a safe condition ia MODE 3.
j:
]
The criteria governing the design and specific system requirements of j
the Remote Shutdown Instrumentation and Controls are located in 10 CFR 50, i
Appendix A GDC 19.
1 LC0 The Remote Shutdown Instrumentation and Controls LC0 provides the i
OPERABILITY requirements of the instrumentation and controls necessary to j
place and maintain the unit in MODE 3 from a location other than the control room. The instrumentation and controls required are listed in Table 3.3-9 in the accompanying LCO.
The controls, instrumentation, and transfer switches are required for:
Reactor trip indication; RCS pressure control; Decay heat removal via the AFW System and the SG safety valves; RCS inventory control via charging flow; and j
i Safety support systems for the above Functions, including auxiliary j
saltwater, component cooling water, and emergency diesel j
generators.
i A remote shutdown Function is OPERABLE if all required instrument and control channels for that function listed in Table 3.3-9 are OPERABLE.
j i
l The remote shutdown instrument and control circuits covered by this LCO j
do not need to be energized to be considered OPERABLE. This LC0 is intended I
to ensure the instraents and control circuits will be OPERABLE if unit l
conditions require that a remote shutdown be performed.
i APPLICABILITY 4
The Remote Shutdown Instrumentation and Controls LC0 is applica61e in l
MODES 1, 2, and 3.
This is required so that the unit can be placed and j
maintained in MODE 3 for an extended period of time from a location other than j
the control room until either control is transferred back to the control room or a cooldown is initiated. This LC0 is not applicable in MODE 4, 5, or 6.
a 1
i i
DIABLO CANYON - UNITS 1 & 2 B 3/4 3-3a Amendment Nos. 94 and 93
INSTRUMENTATION BASES 3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION (Continued)
In these MODES, the facility is already suberitical and in a condition of reduced RCS energy. Under these conditions, considerable time is available to restore necessary instrument control functions if control room instruments or controls become unavailable.
ACTIONS Action a.
Action a. addresses the situation where one or more required Functions (instrument or control) of the Remote Shutdown Instrumentation and Controls are inoperable.
This includes any Function listed in Table 3.3-9, as well as the control and transfer switches.
The Required Action (Action a.) is to restore the required Function to OPERABLE status within 30 days. The Allowed Outage Time (A0T) is based on operating experience and the low probability of an event that would require evacuation of the control room.
If the Required Action and associated A0T of Action a is not met, the unit must be brought to a MODE in which the LC0 does not apply. To achieve i
this status, the unit must be brought to MODE 4 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The A0Ts are l
reasonable, based on operating experience, to reach the required unit l
conditions from full power conditions in an orderly manner and without challenging unit systems.
Action b.
l Action b. excludes the MODE change restriction of TS 3.0.4.
This exception allows entry into an applicable MODE while relying on the ACTIONS even though the ACTIONS may eventually require a unit shutdown. This exception is acceptable due to the low probability of an event requiring remote shutdown and because the equipment can generally be repaired during operation without significant risk of spurious trip.
(
Action c.
Action c.
has been added to the ACTIONS to clarify the application of A0T rules.
Separate Condition entry is allowed for each Function listed on Table 3.3-9.
The A0T(s) of the inoperable channel (s) of a Function will be tracked separately for each Function starting from the time the Condition was entered for that Function.
l l
l DIABLO CANYON - UNITS 1 & 2 B 3/4 3-3b Amendment Nos. 94 and 93
- 4..
1 INSTRUMENTATION i
l BASES l
3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION (Continued)
I j
SURVEILLANCE REQUIREMENTS SR 4.3.3.5.1 1
i Performance of thtWIANNEL rum c;;ce every 31 days ensures that a gross i
failure of instrumentation.M net accurred. A CHANNEL CHECK is a comparison i
of the parameter indicated on one channel to a similar parameter on other channels.
It is based on the assumption that instrument channels monitoring the same parameter should' read approximately the same value. Significant deviations between the two instrument channels could be an indication of j
excessive instrument drift in one of the channels or of something even more serious. CHANNEL CHECK will detect gross channel failure; thus, it is key to j
verifying that the instrumentation continues to operate properly between each CHANNEL CALIBRATION.
i Agreement criteria are determined by the unit staff based on a combination of the channel instrument uncertainties, including indication and i
readability.
If the channels are within the. match criteria, it is an indication that the channels are OPERABLE.
If the channels are'normally'off-scale during times when. Surveillance is' required, the CHANNEL CHECK will j
verify only that they are off scale in the same direction. Offscale low i-current loop channels are verified to be reading at the bottom of the range and not failed downscale.
1 l
The frequency of 31 days is based.upon operating experience which j
demonstrates that channel failure is rare.
j CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. The test verifies that the channel responds to measured parameters with the necessary range'and accuracy.
}
The frequency of 18 months is based upon operating experience and j
consistency with the typical industry refueling cycle.
l SR 4.3.3.5.2 J
SR 4.3.3.5.2 verifies each required Remote Shutdown Instrumentation and
{
Controls control circuit and transfer switch performs the intended function.
This verification is performed from the hot shutdown panel and at other l-locations.for certain control transfer switches, as appropriate. This will ensure that if the control room becomes inaccessible, the unit can be placed and maintained in MODE 3 from the hot shutdown panel and the local control stations. The 18 month-Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with j-the reactor at power.
(However, this Surveillance is not required to be Y
l DIABLO CANYON - UNITS 1 & 2 B3/43-3c Amendment Nos. 94.and 93 4
l l
INSTRUMENTATION l'
BASES 3/4,3.3.5 REMOTE SHUTDOWN INSTRUMENTATION (Continued) perfoned only during a unit outage.) Operating experience demonstrates that remote snutdown control channels usually pass the Surveillance test when performed at the 18 month frequency.
NOTE: A surveillance of the reactor trip breaker OPERABILITY is not required as part of the SURVEILLANCE REQUIREMENT for 4.3.3.5.2 since a TRIP ACTUATING DEVICE OPERATIONAL TEST of the reactor trip breakers is performed as part of the SURVEILLANCE REQUIREMENT for TS 3/4.3.1 (See Table 4.3-1 Item 21 and Note 10).
1 REFERENCES 1.
10 CFR 50, Appendix A, GDC 19.
3/4.3.3.6 ACCIDENT MUNITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident.
The normal plant instrument channels specified are suitable for use as post-accident instruments. This capability is consistent with the recommendations of Regulatory Guide 1.97, l
Revision 3, " Instrumentation for Light-Water-Cooled Nucl ar Power Plants to l
Assess Plant Conditions During and following an Accident," May 1983, and l
NUREG-0737, " Clarification of TMI Action Plan Requirements," November 1980.
l l
3/a.3.3.7 CHLORINE DETECTION SYSTEMS The OPERABILITY of the Chlorine Detection System ensures that sufficient capability is available to promptly detect and initiate protective action in the event of an accidental chlorine release. This capability is required to l
protect control room personnel and is consistent with the recommendations of Regulatory Guide 1.95, " Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release," February 1975.
l I
\\
I l
1 l
DIABLO CANYON - UNITS 1 & 2 B 3/4 3-3d Amendment Nos. 94 and 93