ML20245L236
| ML20245L236 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 04/25/1989 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20245L241 | List: |
| References | |
| NUDOCS 8905050340 | |
| Download: ML20245L236 (17) | |
Text
_ _
f neuQ o,j UNITED STATES
[
g NUCLEAR REGULATORY COMMISSION
,5
- j WASHINGTON, D. C. 20656
...../
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-275 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 36 i
License No. DPR-80 I
1.
The. Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Pacific Gas & Electric Company (the licensee), dated December 24, 1986 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the A ct), and the Comission's regulations set forth in 10 CFR Chapter I; i
B.
The facility will operate in conformity with the ap)11 cation, the provisions of the Act, and the regulations of tie 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 i
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 i
E.
The issuance of thir. amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
i 8905050340 890425 l
PDR ADOCK 05000275 P
PDC i
7, 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.k ) of Facility Operating License No. DPR-80 is hereby amended to read as follows:
Q) Technical Specifications The Technical Specifications' contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 36, 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 becomes effective at the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION yt
/$1e w
George Knighton irector Project Directora V
I Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: April 25,1989 l
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UNITED STATES s
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NUCLEAR REGULATORY COMMISSION 1
P, E
WASHINGTON, D C. 20555
)
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLANT, UNIT 2 DOCKET NO. 50-323 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.35 License No. DPR-82 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Pacific Gas & Electric Company (the licensee), dated December 24, 1986 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the a ct), and the Comission's regulations set forth in 10 CFR Chapter I; B.
The facility will o)erate in conformity with the ap)11 cation, the provisions of t1e Act, and the regulations of t1e Comission; C.
Thereisreasonableassurance(1)thattheactivitiesauthorized 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 ansendment 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 Comission's regulations and all applicable requirements have been satisfied.
I
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.k ) of Facility Operating License No. DPR-82 is hereby amended to read as follows:
Q) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 35, 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 becomes effective at the date of.its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION W
//
tt U
George. Knighton irector Projec Directora V
Division of Reactor Projects. III, IV, Y and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: April 25,1989 i
m__.._--mm_
__um
L 4
ATTACHMENT TO LICENSE AMENDMENT NOS. 36 AND 35 FACILITY OPERATING LICENSE NOS. DPR-80 and DPR-82 DOCKET NOS. 50-275 AND 50-323 Replace the following ) ages of the Appendix "A" Technical Specifications.with the attached pages. T1e revised pages are identified by Amendrent number and
..contain vertical lines indicating the areas of change.
Remove Page Insert Page 3/4 3-10 3/4 3-10 3/4 3-11 3/4 3-11 3/4 3-12 3/4 3-12 3/4 3-13 3/4 3-13 3/4 3-32 3/4 3-32 3/4 3-34 3/4 3-34 3/4 3-35 3/4 3-35 1
l l
I
~
l TABLE 3.3-2 (Continued)
(
REACTOP TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES 1
FUNCTIONAL UNIT RESPONSE TIME I
17.
Turbine Trip a.
Low Fluid Oil Pressure N.A.
b.
Turbine Stop Valve N. A.
18.
Safety Injection Input from ESF N.A.
19.
Reactor Coolant Pump Breaker Position Trip h.A.
20.
Reactor Trip Breakers N.A.
21.
Automatic Trip and Interlock Logic N.A.
22.
Reactor Trip System Interlocks N. A.
23.
Seismic Trip N. A.
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TABLE 4.3-1 (Continued)
TABLE NOTATIONS When the Reactor Trip System brea.kers are closed and the Control Rod Drive System is capable of rod withdrawal.
Below P-6-(Intermediate Range Neutron Flux Interlock) Setpoint.
Below P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.
(1)-
If not perforr.ed in previous 31 days.
(2) -
Heat balance only, above 15% of RATED THERMAL POWER.
During startup.
in MODE 1 above 15% of RATED THERMAL POWER,'the required heat balance shall be performed prior to exceeding 30% of RATED THERMAL POWER, or within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, whichever occurs first.
Adjust channel if absolute difference greater than 2%. The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.
(3) -
Compare incore to excore axial flux difference above 15% of RATED THERMAL POWER at least once per 31 Effective Full Power days.
Re-calibrate if the absolute difference is greater.than or equal to 3%.
The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.
j (4)-
Neutron detectors may be excluded from CHANNEL CALIBRATION.
(5) -
Detector plateau curves shall be obtained and evaluated for the source range neutron flux chanels.
For.the Intermediate Range and Power Range Neutron Flux channels a test shall be performed that shows allowed variances of detector voltage do not effect detector.
operation.
For the Intermediate Range and Power Range Neutron Flux Channels the provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.
(6)-
Incore - Excore Calibration, above 75% of RATED THERMAL POWER at:1 east
- once per 92 Effective Full Power days The provisions of Specifica-tion 4.0.4 are not applicable for entry into MODE 2 or 1.
(7)'-
Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.
(8) -
Quarterly Surveillance in MODES 3*, 4* and 5* shall also include veri-fication that permissives P-6 and P-10 are in their required state for existing plant conditions by observation of the permissive annunciator window.
(9)-
Setpoint verification.is not applicable.
l (10)-
At least once per 18 months and following maintenance or adjustment l
of the Reactor trip breakers, the TRIP ACTUATING DEVICE OPERATIONAL TEST shall include verification of the independence of the Undervoltage trip and the Shunt trip.
(11)-
CHANNEL CALIBRATION shall include the RTD bypass loops flow rate.
l (12)-
Each channel shall be tested at least every 92 days on a STAGGERED TEST BASIS.
4 (13) -
These channels also provide inputs to ESFAS.
Comply with the appli-l cable MODES and surveillance frequencies of Specification 4.3.2.1 for any portion of the channel required to be OPERABLE by
{
Specification 3.3.2.
q i
)
DIABLO CANYON - UNITS 1 & 2 3/4 3-13 Amendment Nos. 36 and 35 I
INSTRUMENTATION 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2 The Engineered Safety Features Attuation System (ESFAS) instrumentation channels and interlocks shown in Table 3.3-3 shall be OPERABLE with their Trip Setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4 and with RESPONSE TIMES as shown in Table 3.3-5.
APPLICABILITY: As shown in Table 3.3-3.
ACTION:
With an ESFAS Instrumentation Channel or Interlock Trip Setpoint less d.
conservative than the value shown in the Allowable Values column of Table 3.3-4, decla.. the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the Trip Setpoint adjusted consistent with the Trip Setpoint value.
b.
With an ESFAS instrumentation channel or interlock inoperable, take the ACTION shown in Table 3.3-3.
SURVEILLANCE REQUIREMENTS 4.3.2.1 Each ESFAS instrumentation channel and interlock and the automatic actuation logic and relays shall be demonstrated OPERABLE by the performance of the Engineered Safety Feature Actuation System Instrumentation Surveillance Requirements specified in Table 4.3-2.
4.3.2.2 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS function shall be demonstrated to be within the limit at least once per 18 months.
Each test shall include at least one train such that both trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once per N times 18 months where N is the total number of redundant channels in a specific ESFAS function as shown in the " Total No. of Channels" column of Table 3.3-3.
1 DIABLO CANYON - UNITS 1 & 2 3/4 3-14 4
ECVR 2 2 2
2 2 2
2 2 2 2 DIR OHUS MWSI 1 1 1
1 1 1
1 1 1 1 EY VAT ALS A.
A.
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e TABLE 3.3-5 (Continued) j f
TABLE NOTATIONS (1) Diesel generator starting and sequence loading delays included.
Response
time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps, SI and RHR pumps
]
(where applicable).
(1) Feedwater System overall response time shall include verification of each individual Feedwater System valve closure time as shown below:
Closure Time (not including Valve instrumentation delays)
FCV-438
< 60 seconds 439 7 60 seconds 440 7 60 seconds 441 7 60 seconds 510 7 5 seconds 520 7 5 seconds 530 7 5 seconds 540 7 5 seconds 1510 7 5 seconds 1520 7 5 seconds 1530 7 5 seconds 1540 55 seconds (3) Diesel generator starting and loading delays included.
(4) Diesel generator starting and sequence, loading delays not included.
Offsite power available.
Response time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps (where applicable).
(5) Diesel generator starting and sequence loading delays included.
Response
time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps.
(6) The maximum response time of 48.5 seconds is the time from when the con-tainment pressure exceeds the High-High Setpoint until the spray pump is started and the discharge valve travels to the fully open position assuming off site power is not available.
The time of 48.5 seconds includes the 28-second maximum delay related to ESF loading sequence.
Spray riser piping fill time is not included.
The 80-second maximum spray delay time does not include the time from LOCA start to "P" signal.
l DIABLO CANYON - UNITS 1 & 2 3/4 3-31 1
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' INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING FOR PLANT OPERATIONS LIMITING CONDITION FOR OPERATION 3.3.3.1 The radiation monitoring instrumentation channels for plant operations shown in Table 3.3-6 shall be OPERABLE with their Alarm / Trip Setpoints within the specified limits.
APPLICABILITY:
As shown in Table 3.3-6.
ACTION:
a.
With a radiation monitoring channel Alarm / Trip Setpoint 'r plant operations exceeding the value shown in Table 3.3-6, ar;j.;t the Setpoint to within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the channel inoperable.
b.
With one or more radiation monitoring channels for plant operations inoperable, take the ACTION shown in Table 3.3-6.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel for plant operations shall be demonstrated OPERABLE by the performance of the CF.ANNEL CHECK, CHANNEL CALIBRATION a.d CHANNEL FUNCTIONAL TEST for the MODES and at the frequencies shown in Tab 1: 4.3-3.
l l
DIABLO CANYON - UNITS 1 & 2 3/4 3-36
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