ML20210P236
| ML20210P236 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 01/30/1987 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20210P240 | List: |
| References | |
| TAC-62158, NUDOCS 8702130339 | |
| Download: ML20210P236 (14) | |
Text
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UNITED STATES O'
NUCLEAR REGULATORY COMMISSION 3
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PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLANT, UNIT 1 DOCKET N0. 50-275 AMENDMENT TO FACILITY'0PERATING LICENSE Amendment No. 12 License No. DPR-80 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment dated July 18, 1986 (LAR 86-08), by Pacific Gas & Electric Company (the licensee) complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter 1; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; 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 Comission'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 t
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by a change to the combined Technical Specifications for Units 1 and 2 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:
i l
8702130339 870130 l
PDR ADOCK 05000275 P
. (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.12, and the Environmental Protection Plan contained in Appendix B are hereby incorporated in the license.
PG&E shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment becomes effective at the date of its issuance.
FOR THE NUCLE REGULATORY C0f*ISSION a'r a, PWR Project Dire,Di ec r
en to -te #3 Division of PWR L ing-A, NRR
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 30, 1987 l
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PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAP, POWER PLANT, UNIT 2 DOCKET NO. 50-323 AMFNDMENT T0 FACILITY OPERATING LICENSE Amendment No. 10 License No. DPP-82 1.
The Nuclear Regulatory Connission (the Commission) has found that:
1 A.
The application for amendment dated July 18, 1986 (LAP. 85-08),
by Pacific Gas & Electric Company (the licensee) complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Connission's rules and regulations set forth in 10 CFR Chapter 1; B.
The facility will operate in conformity with the application, as amended..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 Comission'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 l
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements l
have been satisfied.
i 2.
Accordingly, the license is amended by a change to the combined Technical l
Specifications for Units 1 and 2 as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. OPR-82 is hereby amended to read as follows:
i
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(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 10, and the Environmental
. Protection Plan contained in Appendix B are hereby incorporated in the license.
PG&E shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment becomes effective at the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 3
. Va or PWR Project Directo ate #3 Division of PWR Lice in_-A, NPR
Attachment:
Changes tc the Technical Specifications t
Date of Issuance:
January 30, 1987 l
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g-di UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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ATTACHMENT TO LICENSE AMENDMENT NOS.12 Ah'D 10 FACILITY OPERATING LICENSE NOS. DPR-80 AND DPR-82 DOCKET NOS. 50-275 AND 50-323 Revise the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment Number and contain vertical lines indiciating the area of change.
Remove Pages Insert Paces y
v xiv xiv 3/4 2-1 3/4 2-1 3/4 2-la 3/4 2-lb 3/4 2-2 3/4 2-2 3/4 2-3 3/4 2-3 3/4 2-4 3/4 2-4 B3/4 2-1 B3/4 2-1 B3/4 2-2 83/4 2-2 B3/4 2-3 B3/4 2-3
~
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION
_P_ age 3/4.1 REACTIVITY CONTROL SYSTEMS (Continued)
FIGURE 3.1-la ROD BANK INSERTION LIMITS VERSUS THERMAL POWER (UNIT 1).........................................
3/4 1-23 FIGURE 3.1-lb ROD BANK INSERTION LIMITS VERSUS THERMAL POWER (UNIT 2).........................................
3/4 1-24 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE..................................
3/4 2-1 FIGURE 3.2-la AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER (Unit 1)......................
3/4 2-2 FIGURE 3.2-lb AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER (Unit 2)......................
3/4 2-3 3/4.2.2 HEAT FLUX HOT CHANNEL FACT 0R-F (Z).....................
3/4 2-5 q
FIGURE 3.2-2 K(Z) - NORMALIZED F HEIGHT............ 9.(Z) AS A FUNCTION OF CORE 3/4 2-6 3/4.2.3 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACT 0R.....................................
3/4 2-9 FIGURE 3.2-3a RCS TOTAL FLOWRATE VERSUS R (UNIT 1)..............
3/4 2-10 FIGURE 3.2-3b RCS TOTAL FLOWRATE VERSUS R (UNIT 2)..............
3/4 2-11 3/4.2.4 QUADRANT POWER TILT RATI0..............................
3/4 2-13 3/4.2.5 DNB PARAMETERS.........................................
3/4 2-16 TABLE 3.2-1 DNB PARAMETERS......................................
3/4 2-17 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION....................
3/4 3-1 TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION.................
3/4 3-2 TABLE 3.3-2 REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES..
3/4 3-8 TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS...........................................
3/4 3-10 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION........................................
3/4 3-14 l
TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION........................................
3/4 3-15 DIABLO CANYON - UNITS 1 & 2 v
Amendment Nos.12 and 10 I
l
INDEX BASES SECTION PAGE 3/4.0 APPLICABILITY..............................................
B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS
^
3/4.1.1 BORATION CONTR0L.........................................
B 3/4 1-1 3/4.1.2 BORATION SYSTEMS.........................................
B 3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES...............................
B 3/4 1-3 3/4.2 POWER DISTRIBUTION LIMITS..................................
B 3/4 2-1 3/4.2.1 AXIAL FLUX DIFFERENCE....................................
B 3/4 2-1 3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR, and RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR........
B 3/4 2-2 3/4.2.4 QUADRANT POWER TILT RATI0................................
B 3/4 2-5 3/4.2.5 DNB PARAMETERS...........................................
B 3/4 2-6 3/4.3 INSTRUMENTATION 3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION................
B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION...............................
B 3/4 3-2 3/4.3.4 TURBINE OVERSPEED PROTECTION.............................
B 3/4 3-5 l
3/4.4 REACTOR COOLANT SYSTEM l
3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION............
B 3/4 4-1 3/4.4.2 SAFETY VALVES............................................
B 3/4 4-1 3/4.4.3 PRESSURIZER..............................................
B 3/4 4-2 3/4.4.4 RELIEF VALVES............................................
B 3/4 4-2 3/4.4.5 STEAM GENERATORS.........................................
B 3/4 4-2 DIABLO CANYON - UNITS 1 & 2 xiv Amendment Nos.12and 10
4 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE LIMITING CONDITIONS FOR OPERATION 3.2.1 The indicated AXIAL FLUX DIFFERENCE (AFD) shall be maintained within the allowed operational space defined by Figure 3.2-la for Unit 1, and Figure 3.2-lb for Unit 2.
APPLICABILITY: MODE 1 ABOVE 50 PERCENT RATED THERMAL POWER *.
ACTION:
a.
With the indicated AXIAL FLUX DIFFERENCE outside of the Unit 1 Figure 3.2-la limits e-Unit 2 Figure 3.2-lb. limits, l
1.
Either restore the indicated AFD to within the Unit 1 Fig-ure 3.2-la or Unit 2 Figure 3.2-lb limits within 15 minutes, or l
2.
Redace THERMAL POWER to less than 50% of RATED THERMAL POWER within 30 minutes and reduce the Power Range Neutron Flux - High l
Trip setpoints to less than or equal to 55 percent of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
b.
THERMAL POWER shall not be increased above 50% of RATED THERMAL POWER unless the indicated AFD is within the Unit 1 Figure 3.2-la or Unit 2 Figure 3.2-1b limits.
SURVEILLANCE REQUIREMENTS 4.2.1.1 The indicated AXIAL FLUX DIFFERENCE shall be determined to be within its limits during POWER OPERATION above 50 percent of RATED THERMAL POWER by:
a.
Monitoring the indicated AFD for each OPERABLE excore channel:
1.
At least once per 7 days when the AFD Monitor Alarm is OPERABLE, and 2.
At least once per hour for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after restoring the AFD Monitor Alarm to OPERABLE status.
b.
Monitoring and logging the indicated AXIAL FLUX DIFFERENCE for each OPERABLE excore channel at least once per hour for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and at least once per 30 minutes thereafter, when the AXIAL FLUX DIFFERENCE Monitor Alarm is inoperable.
The logged values of the indicated AXIAL FLUX DIFFERNECE shall be assumed to exist during the l
interval preceding each logging.
+
4.2.1.2 The indicated AFD shall be considered outside of its limits when at l
least 2 OPERABLE excore channels are indicating the AFD to be outside the limits.
- See Special Test Exceptions Specification 3.10.2 DIABLO CANYON - UNITS 1 & 2 3/4 2-1 Amendment Nos.12 and 10
UNIT 1 I
(-13.100)
(6.100) i 5 UNACCEPTABLE UNACCEPTABLE g OPERATION
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OPERATION g
k i
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81.
60 i
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2 5
C i
W I
5 ACCEPTABLE i
60 5
OPERATION O
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b-(-29,60)
(21.60) 1 40 0
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20 UNIT 1 0
i 1
-60
-40
-30
-20
-10 0
10 20 30 40 60 l
FLUX DIFFERENCE (AD%
FIGURE 3.2-la UNIT 1 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER DIABLO CANYON - UNITS 1 & 2 3/4 2-2 Amendment Nos.12 and 10 i
,.. - -. -.. _.,---..---_,.--.,,---- -,- -- --~. -..,._ -----..-.-,---.
UNIT 2
(-13.100)
(6.100) hUNACCEPTABLE k_
UNACCEPTABLE W
E OPERATION OPERATION 5
O i
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J E
i E
W I
ACCEPTABLE F
60 f
OPERATON O
i W
f H
g
(-29.50)
(21.50) k 40 o
aR 20 UNIT 2 e
0
-60
-40
-30
-20
-10 0
10 20 30 40 60 l
FLUX DIFFERENCE (AD%
l FIGURE 3.2-lb UNIT 2 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER l
DIABLO CANYON - UNITS 1 & 2 3/4 2-3 Amendment Nos.12 and 10 l
l
1 THIS PAGE INTENTIONALLY LEFT BLANK l
DIABLO CANYON - UNITS 1 & 2 3/4 2-4 Amendment Nos.12 and 10 l
.s 3/4.2 POWER DISTRIBUTION LIMITS BASES The specifications of this section provide assurance of fuel integrity during Condition I (Normal Operation) and II (Incidents of Moderate Frequency) events by:
(a) maintaining the minimum DNBR in the core greater than or equal to 1.30 during normal operation and in short term transients, and (b) limiting the fission gas release, fuel pellet temperature and cladding mechanical properties to within assumed design criteria.
In addition, limiting the peak linear power density during Condition I events provides assurance that the initial conditions assumed for the LOCA analyses are met and the ECCS acceptance criteria limit of 2200'F is not exceeded.
The definitions of certain hot channel and peaking factors as used in these n.pecifications are as follows:
F (Z)
Heat Flux Hot Channel Factor, is defined as the maximum local heat q
flux on the surface of a fuel rod at core elevation Z divided by the average fuel rod heat flux, allowing for manufacturing tolerances on fuel pellets and rods; F
Nuclear Enthalpy Rise Hot Channel Factor, is defined as the ratio of H
the integral of linear power along the rod with the highest integrated power to the average rod power; and Fxy(Z)
Radial Peaking Factor, is defined as the ratio of peak power density to average power density in the horizontal plane at core elevation Z.
3/4.2.1 AXIAL FLUX DIFFERENCE The limits on AXIAL FLUX DIFFERENCE assure that the F (Z) upper bound enve-limit 9
lope of F times the ns.,mnalized axial peaking factor is not exceeded during q
either normal operation or in the event of xenon redistribution following power changes.
Provisions for monitoring the AFD on an automatic basis are derived from the plant process computer through the AFD Monitor Alarm. The computer determines the one minute average of each of the OPERABLE excore detector outputs and provides an alarm message immediately if the AFD for at least 2 of 4 or 2 of 3 l
OPERABLE excore channels are outside the AFD limits and the THERMAL POWER is j
greater than 50 percent of RATED THERMAL POWER.
DIABLO CANYON - UNITS 1 & 2 8 3/4 2-1 Amendment Nos.12 and 10 i
s
.s POWER DISTRIBUTION LIMITS BASES 3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR, and RCS FLOWRATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR The limits on Heat Flux Hot Channel Factor, RCS Flowrate, and Nuclear Enthalpy Rise Hot Channel Factor ensure that:
(1) the design limits on peak local power density and minimum DNBR are not exceeded, and (2) in the event of a LOCA the peak fuel clad temperature will not exceed the 2200*F ECCS acceptance criteria limit.
DIABLO CANYON - UNITS 1 & 2 B 3/4 2-2 Amendment Nos.12and 10
THIS PAGE INTENTIONALLY LEFT BLANK 9
r DIABLO CANYON - UNITS 1 & 2 B 3/4 2-3 Amendment Nos.12and 10
_ - - _