ML20210B884
| ML20210B884 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  (NPF-10-A-057, NPF-10-A-57, NPF-15-A-046, NPF-15-A-46) |
| Issue date: | 01/20/1987 |
| From: | Rood H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20210B890 | List: |
| References | |
| TAC-54728, TAC-54729, NUDOCS 8702090258 | |
| Download: ML20210B884 (13) | |
Text
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UNITED STATES p,
NUCLEAR REGULATORY COMMISSION 3
9j WASHINGTON, D. C. 20555
/
SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CALIFORNIA THE CITY OF ANAHEIM, CALIFORNIA DOCKET NO. 50-361 SAN ON0FRE NUCLEAR GENERATING STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 57 License No. NPF-10 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applications for amendment to the license for San Onofre Nuclear Generating Station, Unit 2 (the facility) filed by the Southern California Edison Company on behalf of itself and San Diego Gas and Electric Company, The City of Riverside and the City of Anaheim, California (licensees) dated March 2 and April 2, 1984 comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; j
B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Commission; i
C.
There is reasonable assurance:
(1) that the activities authorized by this amendment can be conducted without endangering the health l
and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the common defense and security or to the health ano safety of the public; 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.
8702090258 870120 DR ADOCK 0500 1
V
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this amendment and Paragraph 2.C(2) of Facility Operating License No. NPF-10 is hereby dmended 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. 57, are hereby incorporated in the license.
SCE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The changes in Technical Specifications are to become effective within 30 days of issuance of the amendment.
In the period between issuance of the amendment and the effective date of the new Technical Specifications, the licensees shall adhere to the Technical Specifications existing at the time. The period of time during change over shall be minimized.
4.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l
Harry Rood, Senior Project Manager l
PWR Project Directorate No. 7 Division of PWR Licensing-B
Attachment:
Changes to the Technical Specifications l
Date of Issuance: January 20, 1987 l
N
January 20 1987 0
.3-ATTACHMENT TO LICENSE AMENDMENT NO. 57 FACILITY OPERATING LICENSE P0. NPF-10 DOCKET NO. 50-361 Replace 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 indicating the area of change. Also to be replaced are the following overleaf pages to the amended pages.
Amendment Pages Overleaf Pages 3/4 3-63 3/4 3-64 3/4 3-65 l
l l
I
p INSTRUMENTATION RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alare/ trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded.
The alarm /
trip setpoints of these channels shall be determined in accordance with the 0FFSITE DOSE CALCULATION MANUAL (0DCM).
APPLICABILITY: At all times.*
ACTION:
With a radioactive liquid' effluent monitoring instrumentation a.
channel alarm / trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.
b.
With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12.
Exert best efforts to return the instrument to OPERABLE status within 30 days and, additionally, if the inoperable instrument (s) remain inoperable for greater than 30 days, explain-in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.
1 c.
The provisions of Specifications 3.0.3, 3.0.4, and 6.9.1.13b are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.8.1 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE l
CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-8.
4.3.3.8.2 At least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, all pumps required to be providing dilu-tion to meet the site radioactive effluent concentration limits of Specifica-tion 3.11.1.1 shall be determined to be operating and providing dilution to the discharge structure.
i "See Special Test Exception 3.10.5.
SAN ONOFRE-UNIT 2 3/4 3-63 AMENDMENT N0. 57 s
,,,--,--,-n,.
v-.-e
,,-.,,,-m.
-,_.,m---
mmm n
v w
w
-w
,--,m,ww-r
m E
TABLE 3.3-12 l
RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION i2 E
MINIMUM Z
CHANNELS INSTRUMENT OPERABLE ACTION m
1.
GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE a.
Liquid Radwaste Effluent Line - 2/3 RT - 7813 1
28 b.
Steam Generator Blowdown (Neutralization Sump)
Effluent Line - 2RT - 7817 1
29 c.
Turbine Building Sumps Effluent Line - 2RT - 7821 1
30 w
A d.
Steam Generator (E086) Blowdown Bypass Effluent Line -
1 29 w
I a
2RT6759
+
e.
Steam Generator (E089) Blowdown Bypass Effluent Line -
1 29 j
2RT6753 2.
FLOW RATE MEASUREMENT DEVICES a.
Liquid Radwaste Effluent Line 1
31 b.
Steam Generator Blowdowr. (Net:tralization Sump)
Effluent Line 1
31 N=
c.
Steam Generator (E088) Blowdown Bypass Effluent Line 1
31 Eg d.
Steam Generator (E089) Blowdown Bypass Effluent Line 1
31 5
l 9
t a
4
[-
L TABLE 3.3-12 (Continued)
TABLE NOTATION l
ACTION 28 -
With the number of channels OPERABLE less than required by the l
Minimum Channels OPERABLE. requirement, effluent releases may continue provided that prior to initiating a release:
l a.
At least two independent samples are analyzed in accordance with Specification 4.11.1.1.3, and b.
At least two technically qualified members of the Facility L
Staff independently verify the release rate calculations and discharge line valving; Otherwise, suspend release of radioactive effluents via this pathway.
I ACTION 29 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for l
grossradiogytivity(betaorgamma)atalimitofdetectionof.
at least 10 microcuries/ gram:
a.
At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when the specific activity of the secondary coolant is greater than 0.01 microcuries/
gram DOSE EQUIVALENT I-131; b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity R
of the secondary / gram DOSE EQUIVALENT I-131; or coolant is less than or equal to O.01 microcuries c.
Lock closed valve HV-3773 and divert flow to T-064 for pro-cessing as liquid radwaste.
ACTION 30 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that, at least once per l
8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, grab samples are collected and analyzed for gross radio-acijvity(betaorgamma)atalimitofdetectionofatleast 10 microcuries/ml or lock closed valve S22U19-MUO77 or 522U19-MUO78 and divert flow to the radwaste sump for processing L
as liquid radwaste.
T l
ACTION 31 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via j
this pathway may continue provided the flow rate is estimated at l
least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.
Pump curves may i
be used to estimate flow.
i a
i SAN ONOFRE-UNIT 2 3/4 3-65 AMENDMENT N0. 57
F p2teru
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- UNITED STATES
+
g NUCLEAR REGULATORY COMMISSION j
WASHINGTON, D. C. 20655 5
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SOUTHERN CALIFORNIA EDIS0N COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CALIFORNIA THE CITY OF ANAHEIM, CALIFORNIA DOCKET NO. 50-362 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 46 License No. NPF-15 1.
The Nuclear pegulatory Comission (the Commission) has found that:
A.
The applications for amendment to the license for San Onofre Nuclear Generating Station, Unit 3 (the facility) filed by the Southern California Edison Company on behalf of itself and San Diego Gas and Electric Company, The City of Riverside and the City of Anaheim, California (licensees) dated March 2 and April 2, 1984 comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR_ Chapter I; 8.
The facility will operate in conformity with the application, as l
amended, the provisions of the Act, and the regulations of the Commission; C.
There is reasonable assurance:
(1) 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 set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; 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.
L
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this amendment and Paragraph 2.C(2) of Facility Operating License No. NPF-15 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. 46, are hereby incorporated in the license.
SCE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The changes in Technical Specifications are to become effective within 30 days of issuance of the amendment.
In the period between issuance of the amendment and the effective date of the new Technical Specifications, the licensees shall adhere to the Technical Specifications existing at the time. The period of time during change over shall be minimized.
4.
This license amendment is effective as of the date of its issuance.
I FOR THE NUCLEAR REGULATORY COMMISSION I
r TW l
l Harry Roo, Senior Project Manager
(
PWR Project Directorate No. 7 Division of PWR Licensing-B
Attachment:
Changes to the Technical Specifications l
Date of Issuance: January 20, 1987 l
l 1
l l
l
P
[ '-
January 20, 1987
-3 i
f ATTACHMENT TO LICENSE AMENDMENT N0. 46 FACILITY OPERATING LICENSE NO. NPF 15 DOCKET NO. 50-362 Replace 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 indicating the area of change. Also to be replaced are the following overleaf pages to the amended pages.
i Amendment Page Overleaf Page 3/4 3-64 3/4 3-63 l
3/4 3-66 3/4 3-65 1
l l
q
TABLE 3.3-11 (Continued)
(
Zone Instrument Location Early Warning Actuation HEAT FLAME SMOKE HEAT FLAME SM0KE 78 Control Building Elev 9' Corridor Rm 105 4
l 79 Control Buildin<2 Elev 50' ESF Switchgear its 302A 2
ESF Switchgear Rm 302B 2
80 Radwaste Elev 37' & 50' Duct Shaft Rms None 81 Radwaste Elev 63'6" Duct Shaft Ras 527A,B None 83 Salt Water Cooling Tunnel 6*
84 Safety Eqamt Blda Elev 8' l
HVAC Rm 017 3
Technical Support Center (TSC) 5 1 (Note 3)
(
- 3 in UNIT 2, 3 in UNIT 3 Notes 1.
On completion of DCP 3-403E 2.
On completion of DCP 3-122M 3.
On completion of DCP 2-403E l
l
(
SAN ONOFRE-UNIT 3 3/4 3-63 AMENDMENT NO. 8
i INSTRUMENTATION RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded. The alarm /
trip setpoints of these channels shall be determined in accordance with the 0FFSITE DOSE CALCULATION MANUAL (ODCM).
4 APPLICABILITY: At all times.
ACTION:
a.
With a radioactive liquid effluent monitoring instrumentation channel alare/ trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.
b.
With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12.
Exert t est efforts to return the instrument to OPERABLE status within 30 days and, additionally, if the inoperable instrument (s) remain inoperable for greater than 30 days, explain in 4
the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.
c.
The provisions of Specifications 3.0.3, 3.0.4, and 6.9.1.13b are not applicable.
SURVEILLANCE REQUIREMENTS 4
4.3.3.8.1 Each radioactive liquid effluent monitoring instrumentation channel -
shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-8.
4.3.3.8.2 At least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, all pumps required to be providing dilu-tion to meet the site radioactive effluent concentration limits of Specifica-tion 3.11.1.1 shall be determined to be operating and providing dilution to the discharge structure.
f SAN ONOFRE - UNIT 3 3/4 3-64 AMENDMENT NO. 46
~
m n
TABLE 3.3-12
[
RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION aa rp MINIMlm c
CHANNELS l
g INSTRUMENT OPERABLE ACTION i
1.
GROSS RADI0 ACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE i
a.
Liquid Radwaste Effluent Line - 2/3 RT - 7813 1
28 l
b.
Steam Generator Blowdown (Neutralization Sump)
Effluent Line - 3RT - 7817 1
29 c.
Turbine Building Sumps Effluent Line - 3RT - 7821 1
30 w>
d.
Steam Generator (E088) Blowdown Bypass Effluent w
Line - 3RT6759 1
29 cA Steam Generator (E089) Blowdown Bypass Effluent e.
Line - 3RT6753 1
29
~
2.
FLOW RATE MEASUREMENT DEVICES a.
Liquid Radwaste Effluent Line 1
31 b.
Steam Generator Blowdown (Neutralization Sump)
Effluent Liiie 1
31 Steam Generator (E088) Blowdown Bypass Effluent Li.ne 1
31 c.
3mg d.
Steam Generator (E089) Blowdown Bypass Effluent Line 1
31
~
5
=-
TABLE 3.3-12 (Continued)
TABLE NOTATION ACTION 28 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided that prior to initiating a release:
a.
At least two independent samples are analyzed in acc.ordance with Specification 4.11.1.1.3, and b.
At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving; Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 29 -
With the number of channels OPERABLE less than required by.the i
Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for l
grossradjoactivity(betaorgamma)atalimitofdetectionofat least 10 microcuries/ gram:
+
a.
At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when the specific activity of the secondary coolant is greater than 0.01 microcuries/
gram DOSE EQUIVALENT I-131.
b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary / gram DOSE EQUIVALENT I-131; or coolant is less than or equal to 4
0.01 microcuries i
c.
Lock closed valve HV-3773 and divert flow to T-064 for processing as liquid radwaste.
i ACTION 30 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that, at least once per l
8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, grab samples are collected and analyzed for gross I
l radioactlyity (beta or gamma) at a limit of de.tection of at i
least 10 microcuries/ml or lock closed valve S22U19-MUO77 or S22U19-MUO78 and divert flow to the radwaste sump for processing as liquid radwaste.
l ACTION 31 -
With the number of channels OPERABLE less than required by the i
Minimum Channels OPERABLE requirement, effluent releases via this. pathway may continue provided the flow rate is estimated I
at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.
Pump curves may be used to estimate flow.
l SAN ONOFRE - UNIT 3 3/4 3-66 AMENDMENT NO.46 t