ML20245H692
| ML20245H692 | |
| Person / Time | |
|---|---|
| Site: | Salem, Diablo Canyon  |
| Issue date: | 04/14/1989 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20245H697 | List: |
| References | |
| NUDOCS 8905030484 | |
| Download: ML20245H692 (11) | |
Text
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Lecog UNITED STATES e-
[
g NUCLEAR REGULATORY COMMISSION 5
Sj WASHINGTON, D. C. 20555
%...../
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-275 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 35 License No. DPR-80 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Pacific Gas & Electric Company (thelicensee),datedMarch 13, 1987, 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 tie Act, and the regulations of t1e Comission; C.
Thereisreasonableassurance(i)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 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 i
i of the Comission's regulations and all applicable requirements have been satisfied.
i l
8905030484 890414 ADOCK0500g5 PDR P
i
4
. 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:
(2) Technical Specifications The Technical Specifications contained ir 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 f(lf/kW} u George X. KnightgW, Director Project Directorate V Division of Reactor Projects - III/IV/V and Special Projects Office of Nuclear Reactor Regulation i
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 14, 1989
j'* "%
[
gi NUCLEAR REGULATORY COMMISSION 7.
- j WASHINGTON, D. C. 20555 4,
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PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLANT. UNIT 2 DOCKET NO. 50-323 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 34 License No. DPR-82 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Pacitic Gas & Electric Company (the licensee), dated March 13, 1987, complies with the standards and-requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 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 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 Comission's regulations and all applicable requirements have been satisfied.
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l
. 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:
(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.
34, 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 otierwise stated in specific license conditions.
3.
This license amendment becomes effective at the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/Jttg/h George W. Knighton3 irector Project Directorate V 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 14, 1989 I
l l
i ATTACHMENT TO LICENSE AMENCMENT NOS.35 AND 34 FACILITY OPERATING LICENSE NOS. DPR-80 and DPR-82 i
DOCKET NOS. 50-275 AND 50-323 I
Replace the following aages of the Appendix "A" Technical Specification.s with the attached pages. T1e revised pages are identified by Amendment number and contain vertical lines indicating the areas of change. Overleaf paget are provided for the inserted pages, as appropriate.
I Remove Page Insert Page j
3/4 3-5 3/4 3-5 i
3/4 3-13 3/4 3-13 3/4 7-14 3/4 7-14 4
1
TABLE 3.3-1 (Continued)
TABLE NOTATIONS i
- When the Reactor Trip System breakers are in the closed position and the Control Rod Drive System is capable of rod withdrawal.
- The provisions of Specification 3.0.4 are not applicable.
N Below the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.
- elow the P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.
B (1)These channels also provide inputs to ESFAS.
Comply with the applicable MODES and ACTION statements of Specification 3.3.2 for any portion of the l
channel required to be OPERABLE by Specification 3.3.2.
l ACTION STATEMENTS ACTION 1 - With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel 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 STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:
l t
The inoperable channel is placed in the tripped condition a.
within 6 %ers, b.
The Minwnum Channels OPERABLE requirement is met; however, the inoperable chanr.el may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing per Specification 4.3.1.1, and Either, THERMAL POWER is restricted to less than or equal to 75%
c.
of RATED THERMAL POWER and the Power Range Neutron Flux Trip Setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; or, the QUADRANT POWER TILT RATIO is monitored per Specification 4.2.4.2 when THERMAL POWER is greater than or equal to 50% of RATED THERMAL POWER.
l DIABLO CANYON - UNITS 1 & 2 3/4 3-5 Amendment Nos. 3.5.and 34
i TABLE 3.3-1 (Continued)
ACTION STATEMENTS (Continued) 1 ACTION 3 - With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:
l Below the P-6 (Intermediate Range Neutron' Flux Interlock) a.
Setpoint,-restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint, and b.
Above the P-6 Setpoint, but below 10% of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 10% of RATED THERMAL POWER.
ACTION 4 - With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement suspend all operations involving positive reactivity changes.
ACTION 5 - With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement, verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within I hour and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.
ACTION 6 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:
The inoperable channel is placed in the tripped cor.dition a.
within 6' hours, and b.
The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.1.1.
ACTION 7 - With the number of OPERABLE channels less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the inoperable channel (s) is (are) placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
ACTION 8 - With less than the Minimum Number of Channels OPERABLE, within I hour determine by observation of the associated permissive annun-clator window (s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.
i b
DIABLO CANY3N - UNITS 1 & 2 3/4 3-6 Amendment Nos 4 and 2
TABLE 4.3-l'(Continued)
TABLE NOTATIONS When the Reactor Trip System breakers are closed and the Control Rod Drive System is capable of red withdrawal.
Below P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.
' Below P.-10 (Low Setpoint Power Range Neutron Flux. Interlock) Setpoint.
(1)-
If not performed 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.
(4) -
Neutron detectors may be excluded from CHANNEL CALIBRATION.
(5) -
Detector plateau curves shall be obtained and. evaluated.
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 least 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 l
BASIS.
(8) -
'The surveillance requirement is not applicable for a reactor startup from MODE 2 or 3.
(9) -
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.
l (10) -
Setpoint verification is not applicable.
I (11)-
At least once per 18 months and following maintenance or adjustment of the Reactor trip treakers, the TRIP ACTUATING DEVICE OPERATIONAL TEST shall include verification of the independence of the Undervoltage trip and the Shunt trip.
4 (12) -
CHANNEL CALIBRATION shall include the RTD bypass loops flow rate.
(13) -
Each channel shall be tasted at least every 92 days on a STAGGERED TEST BASIS.
(14) -
These channels also provide inputs to ESFAS.
Comply with the appli-cable MODES and surveillance frequencies of Specification 4.3.2.1 for j
any portion of the channel required to be OPERABLE by Specification 3.3.2.
t DIABLO CANYON - UNITS 1 & 2 3/4 3-13 Amendment Nos. 35 and 34
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INSTRUMENTATION j
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3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION j
j LIMITING CONDITION FOR OPERATION 3.3.2 The Engineered Safety Features Actuation 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, declare 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.sith the Trip Setpoint value, b.
With an ESFAS instrumentation channel or interlock inoperable, take the ACTION shown in Table 3.3-3.
SURVEILLANCE REQUIREMENTS i
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 leart 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 o
Channels" column of Table 3.3-3.
l DIABLO CANYON - UNITS 1 & 2 3/4 3-14
)
PLANT SYSTEMS 3/4.7.5 CONTROL ROOM VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.7.5.1 The Control Room Ventilation System
- shall be OPERABLE ** with two l=
separate trains with each train consisting of one main supply fan, one filter l
booster fan, one pressurization supply fan and one HEPA Filter and Charcoal l
Adsorber System.
APPLICABILITY: All MODES.
ACTION:
MODES 1, 2, 3, and 4:
With one Control Room Ventilation System train inoperable, restore the inoperable train to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHbTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
MODES 5 and 6:
a.
With one Control Room Ventilation System train inoperable, restore the inoperable train to OPERABLE status within 7 days or initiate and maintain operation of the OPERABLE Control Room Ventilation System train in the recirculation code.
b.
With both Control Room Ventilation System trains inoperable, or with the OPERABLE Control Room Ventilation System reoutred to be in the recirculation mode by ACTION a. not capable of being powered by an OPERABLE emergency power source, suspend all operations involving CORE ALTERATIONS cr positive reactivity changes.
SURVEILLANCE REQUIREMENTS 4.7.5.1 Each Control Room Ventilation System train shall be demonstrated OPERABLE:
a.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the control room air temperature is less than or equal to 120*F;
- The Control Room Ventilation System is common to both units.
DIABLO CANYON - UNITS 1 & 2 3/4 7-13
r PLANT-SYSTEMS.
I SURVEILLANCE REQUIREMENTS (Continued) b.
At least once per 31 days by:
1)
Initiating flow through the HEPA Filter And Charcoal Adsorber System and verifying that either redundant set of booster and-pressurization supply fans operate for at least 10 continuous hours with the heaters operating, 2)
Verifying that each Ventilation System redundant fan is aligned to receive electrical power from a separate OPERABLE vital bus, and 3)
Starting (unless already operating) each main supply fan, booster fan, and pressurization supply fan, and verifying that it operates for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, At least once per 18 months or (1) after any structural maintenance c.
on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire, or chemical release in any ventilation zone communica-ting with the system by:
1)
. Verifying that the cleanup system. satisfies the in place penetration and bypass leekage testing acceptance criteria cf less than 1% and uses the test procedure guidance in Regulatory Positions C.5.a. C.S.c, and C.5.d of Regulatory Guide 1.52, Revi-sion 2, March 1978, and the system flow rate is 2100 cfm + 10%;
2)
Verifying within 31 days after removal, that a laboratory analysis of a representative carbon sample obtained in accor-
~
dance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revi-sion 2, March 1978, for a methyl iodide penetration of less than 1%; and 3)
Verifying a system flow rate of 2100 cfm + 10% during system operation when tested in accordance with XNSI N510-1980.
d.
After 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation, by verifying, within 31 days after removal, that a laboratory analysis of a' representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52,
'evision 2, March 1978, for a methyl iodide penetration of less than R
1%;
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+.: n DIABLO CANYON - UNITS 1 & 2 3/4 7-14 Amendment Nos. 35 and 34 i
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