ML20207E905
| ML20207E905 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 06/03/1999 |
| From: | Anthony Mendiola NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20207E910 | List: |
| References | |
| NUDOCS 9906070198 | |
| Download: ML20207E905 (10) | |
Text
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1 UNITED STATES g
P; NUCLEAR REGULATORY COMMISSION r
WASHINGTON, D.C. 30006-0001
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QQMMONWEALTH EDISON COMPANY DOCKET NO. 50-373 LASALLE COUNTY STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.133 License No. NPF-11 1.
The_ Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by the Commonwealth Edison Company (the licensee), dated December 2,1996, as supplemented on May 27,1999, 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 I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the 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 set forth in 10 CFR Chapter I;
- 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 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 enclosure to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-11 is hereby amended to read as follows:
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4 9906070199 990603 PDR ADOCK 05000373 p
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(2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.133
, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance and shall be i
implemented prior to the startup of L1C10.
FOR THE NUCLEAR REGULATORY COMMISSION
/5 A thony J. Mendiola, Chief, Section 2 froject Directorate 111
/ Division of Licensing Project Management Office of Nuclear Reactor Regulation i
Attachment:
Changes to the Technical Specifications Date of Issuance: June 3,1999
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ATTACHMENT TO LICENSE AMENDMENT NO.133 i
FACILITY OPERATING LICENSE NO. NPF-11 DOCKET NO. 50-373 i
Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain a vertical line indicating the area of change.
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REMOVE INSERI i
1 3/4 4-5 3/4 4-5 B 3/4 4-2 B 3/4 4-2 i
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REACTOR COOLANT SYSTEM 3/4 4,2 SAFETYIRELIEF VALVES LIMITING CONDITION FOR OPERATION 13.4.2 The safety valve function of 12 of the below listed 13 reactor coolant system safety / relief valves shall be OPERABLE with the specified code safety valve function lift setting *#; all installed valves shall be closed with OPERABLE position indication, a.'
2 L safety / relief valves @1205 psig i3% -
- b. '
3 safety / relief valves @1195 psig *3%
c.
2 safety / relief valves @1185 psig i3%
d.
4 safety / relief valves @1175 psig *3%'
e.
2 safety / relief valves @1150 psig *3%
APPLICABILITY:~ OPERATIONAL CONDITIONS 1,2, and 3.
i i
ACTION.
i a.
With the' safety valve function of one or more of the above required safety / relief valves inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
.With one or more of the above required safety / relief valve stem position indicators i
inoperable, restore the inoperable stem position indicators to OPERABLE status within 7 days or be in at least 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 /> and in
. COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
i SURVEILLANCE REQUIREMENTS-l 4.4.2.1 The safety / relief valve stem position indicators of each safety / relief valve shall be demonstrated OPERABLE by performance of a:
4 a.
. CHANNEL CHECK at least once per 31 days, and a b.
CHANNEL CAllBRATION at least once per 18 months "
. 4.4.2.2 The low-low set function shall be demonstrated not to interfere with the OPERABILITY of the safety / relief valves or the ADS by performance of a CHANNEL CALIBRATION at least once per 18 months..
- The lift setting pressure shall correspond to ambient conditions of the valves at nominal' operating temperatures and pressures. Following testing, lift settings shall be within t1%.
_ #Up to two inoperable valves may be replaced with spare OPERABLE valves with lower -
setpoints until the next refueling outage.
- The provisions of Specification 4.0.4 are not applicable provided the surveillance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure is adequate to perform the test.
LA SALLE - UNIT 1 3/4 4-5 Amendment No.133
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BEN l
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}/J.4.2 SAFETY / RELIEF VALVES-The safety valve function of the safety / relief valves operate to prevent the reactor coolant syntem frcm being pressurized above the Safety Limit of 1325 psig in accordance with the ASME Ccde. Analysis has shown that with the safety function of one of the thirteen safety / relief vaives l
inoperable the reactor pressure is limited to within ASME lll allowable values for the worst case upset transient. Therefore, operation with any 12 SRVs capable of opening is allowable, -
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altnough all installed SRVs must be closed and have position indication to ensure that integrity of the primary coolant boundary is known to exist at all times.
Demonstration of the safety / relief valve lift settings will occur only during shutdown and will be performed in accordance with the provisions of Specification 4.0.5.
j 324.4.3 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.3.1 LEAKAGE DETECTION SYSTEMS The RCS leakage detection systems required by this specification are provided to monitor and detect leakage from the reactor coolant pressure boundary. These detection systems are consistent with the recommendations of Regulatory Guide 1.45, " Reactor Coolant Pressure Boundary Leakage Detection Systems," May 1973.
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3/4 4 3.2 OPERATIONAL LEAKAGE 1
The allowable leakage rates from the reactor coolant system have been based on the I
. piedicted and experimentally observed behavior of cracks in pipes. The normally expected background leakage due to equipment design and the detection capability of the instrumentation fcr determining system leakage was also considered. The evidence obtained from experiments suggests that for leakage somewhat greater than that specified for unidentified leakage the probability is small that the imperfection or crack associated with such leakage would grow rs.pidly. However, in all cases, if the leakage rates exceed the values specified or the leakage is located and known to be PRESSURE BOUNDARY LEAKAGE, the reactor will be shutdown to
- allow further investigation and corrective action.
The Surveillance Requirements for RCS pressure isolation valves provide added
{
assurance of valve integrity thereby reducing the probability of gross valve failure and consequent intersystem LOCA Leakage from the RCS pressure isolation valves is IDENTIFIED j
LIEAKAGE and will be considered as a portion of the allowed limit.
14,4.4 CHEMISTRY
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- The water chemistry limits of the reactor coolant system are established to prevent
' d.nmage to the reactor materials in contact with the coolant. Chloride limits are specified to prevent stress corrosion cracking of the stainless steel. The effect of chloride is not as great
- wben the oxygen concentration in the coolant is low, thus the higher limit on chlorides is parmitted during POWER OPERATION. During shutdown and refueling operations, the te mperature necessary for stress corrosion to occur is not present so high concentrations of chlorides are not considered harmful during these periods.
LA SALLE - UNIT 1 B 3/4 4-2 Amendment No. 133 4
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UNITED STATES g
j NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D.C. 20066 4 001 49.....,d COMMONWEALTH EDISON COMPANY DOCKET NO, 50-374 LASALLE COUNTY STATION. UNIT 2 i
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.118 License No. NPF-18 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by the Commonwealth Edison Company (the licensee), dated December 2,1996, as supplemented on May 27,1999, 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 I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the 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 set forth in 10 CFR Chapter I; 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 E.
The issuance of this amendment is in accordance with 10 CFR Part Si 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 enclosure to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-18 is hereby amended to read as follows:
,s 1
2-(2)
Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.118
, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.-
This license amendment is effective as of the date of its issuance and shall be implemented prior to the startup of L2C9.
FOR THE NUCLEAR REGULATORY COMMISSION nt ny J. Mendiola, Chief, Section 2
/jP ject Directorate til
/ Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications -
Date of tssuance: June 3, 1999
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L' ATTACHMENT TO LICENSE AMENDMENT NO.118 i
FACILITY OPERATING LICENSE NO. NPF-18 DOCKET NO. 50-374 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain a vertical line indicating the area of change.
F_EMOVE INSERT 3/4 4-6 3/4 4-6 B 3/4 4-1a 3/4 4-1a i
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REACTOR COOLANT SYSTEM 3/4.4.2 SAFETY /RFI IEF VALVES LIMITING CONDITION FOR OPERATION 3.4.2 The safety valve function of 12 of the below listed 13 reactor coolant system safety / relief l valves shall be OPERABLE with the specified code safety valve function lift setting *#; all 4
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installed valves shall be closed with OPERABLE position indication.
a.
2 safety / relief valves -@1205 psig i3%
b.
3. safety / relief valves @1195 psig *3%
E c.
_'2_ safety / relief valves @1185 psig *3%
d.
4 ' safety / relief valves @1175 psig 13%
l e.
2. safety / relief valves @1150 psig *3% -
~ APPLICABILITY: OPERATIONAL CONDITIONS 1,2, and 3.
ACTION With the safety valve function of one or more of the above required safety / relief l
- a.
i valves inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD
' SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.'
With one or more of the'above required safety /rclief valve stem position indicators inoperable, restore the inoperable stem position indicators to OPERABLE status within 7 days or be in at least 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 /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.4.2.1 The safety / relief valve stem position indicators of each safety / relief valve shall be demonstrated OPERABLE by performance of a:
a.
CHANNEL CHECK at least once per 31 days, and a
- b.
_ CHANNEL CALIBRATION at least once per 18 months.**
4.4.2.2 The low low set function shall be demonstrated not to interfere with the OPERABILITY i
L
~ f the safety /re!ief valves or the ADS by performance of a CHANNEL CAllBRATION at least o
once per 18 months.
- The lift setting pressure shall correspond 'to ambient conditions of the valves at nominal l
operating temperatures and pressures. Following testing, lift settings shall be within *1%
- #Up to two inoperable valves may be replaced with spare OPERABLE valves with lower setpoints until the next refueling outage.
- The provisions of Specification 4.0.4 are not applicable provided the surveillance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> efter reactor steam pressure is adequate to perform the test.
I LA SALLE-UNIT 2 3/4 4-6 Amendment No.118
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3/4.4.2 SAFETYfRELIEF VALVES The safety valve function of the safety / relief valves operate to prevent the reactor coolant system from being pressurized above the Safety Limit of 1325 psig in accordance with the ASME Code. Analysis has shown that with the safety function of one of the thirteen safety / relief valves l
inoperable the reactor pressure is limited to within ASME Ill allowable values for the worst case upset transient. Therefore, operation with any 12 SRVs capable of opening is allowable, l
although all installed SRVs must be closed and have position indication to ensure that integrity of the primary coolant boundary is known to exist at all times.
Demonstration of the safety / relief valve lift settings will occur only during shutdown and will be performed in accordance with the provisions of Specification 4.0.5.
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LA SALLE - UNIT 2 B 3/4 4-1a Amendment No.118 i