ML20113C104
| ML20113C104 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 06/21/1996 |
| From: | Pickett D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20113C106 | List: |
| References | |
| NPF-62-A-105, RTR-REGGD-01.163, RTR-REGGD-1.163 NUDOCS 9606280217 | |
| Download: ML20113C104 (13) | |
Text
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p uauqk UNITED STATES p
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,j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30086 4001 k
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ILLINDIS POWER COMPANY. ET AL.
DOCKET NO. 50-461 CLINTON POWER STATION. UNIT NO. 1 t
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 105 License No. NPF-62 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Illinois Power Company' (IP),
and Soyland Power Cooperative, Inc. (the licensees) dated Nay 1, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and 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 rules and regulations of the j
Commission; j
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 Commission'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 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 attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-62 is hereby amended to read as follows:
/
' Illinois Power Company is authorized to act as agent for Soyland Power Cooperative, Inc. and has exclusive responsibility and control over the physical construction, operation, and maintenance of the facility.
2Pages 5 and 6 are attached, for convenience, for the composite license to reflect this change.
9606280217 960621 PDR ADOCK 05000461 P
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l 1
i 1 (2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised l
through Amendment No.105, are hereby incorporated into this i~
license.
Illinois Power Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
i D.
The facility requires exemptions from certain requirements of 10 CFR Part 50 and 10 CFR Part 70. These include:
(a) an exemption from the requirements of 10 CFR 70.24 for the criticality alarm monitors around the fuel storage area; (b) an exemption from the requirement of 10 CFR j
Part 50, Appendix J - Option B, paragraph III.B, exempting the measured 1eakage rates from the main steam isolation valves from inclusion in the j
combined leak rate for local leak rate tests (Section 6.2.6 of SSER 6);
i and (c) an exemption from the requirements of paragraph III.B of Option i
B of 10 CFR Part 50, Appendix J, exempting leakage from the valve 4
packing and the body-to-bonnet seal of valve IE51-F374 associated with containment penetration IMC-44 from inclusion in the combined leakage i
rate for penetrations and valves subject to Type B and C tests'(SER supporting Amendment 62 to Facility Operating License No. NPF-62). The j
special circumstances regarding each exemption, except for Item (a) above, are identified in the referenced section of the safety evaluation
+
i, report and the supplements thereto.
l An exemption was previously granted pursuant to 10 CFR 70.24. The exemption was granted with NRC materials license No. SNM-1886, issued November 27, 1985, and relieved IP fr= the requirement of having a criticality alarm system.
IP is hereby exempted from the criticality j
alarm system provision of 10 CFR 70.24 so far as this section applies to the storage of fuel assemblies held under this license.
1 1
These exemptions are authorized by law, will not present an undue risk 4
to the public health and safety, and are consistent with the common i
defense and security. The exemptions in items (b) and (c) above are granted pursuant to 10 CFR 50.12. With these exemptions, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission.
i i
s n
3.
This license amendment is effective as of its date of issuance, to be implemented during the sixth refueling outage.
FOR THE NUCLEAR REGULATORY C0f#ilSSION V
k Douglas V. Pickett, Project Manager Project Directorate III-3 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
I.
License pages 5 and 6 2.
Changes to the Technical Specifications Date of Issuance:
June 21, 1996 P
ATTACHMENT TO LICENSE AMENDMENT NO.105 l*
FACILITY OPERATING LICENSE NO. NPF-62 DOCKET N0. 50-461 i
l Replace the following pages of the License and Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by l
amendment number and contain vertical lines indicating the area of change.
1 Remove Paaes Insert Paaes License License l
5 5
6 6
1.0-3 1.0-3 3.6-2 3.6-2 3.6-8 3.6-8 3.6-17 3.6-17 3.6-18 3.6-18 5.0-16 5.0-16 5.0-16a 1
i i
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. (0) Post-fuel Loadina Initial Test Proaram (Section 14. SER. SSER 5 and SSER 6)
Any changes to the initial test program described in Section 14 of the FSAR made in accordance with the provisions of 10 CFR 50.59 shall be reported in accordance with 50.59(b) within one month of such change.
(9) Eneroency Response Canabilities (Generic Letter 82-33. Sunnlement I to NUREG-0737. Section 7.5.3.1. SSER 5 and SSER 8. and Section 18.
SER. SSER 5 and Safety Evaluation Dated Anril 17. 1987) a.
IP in accordance with the commitment contained in a letter dated December 11, 1986, shall install and have operational separate power sources for each of the fuel zone level channels as provided for in Regulatory Guide 1.97 prior to startup following the first refueling outage.
b.
IP shall submit a detailed control room design final supple-mental summary report within 90 days of issuance of the full power license that completes all the remaining items identified in Section 18.3 of the Safety Evaluation dated April 17, 1987.
D.
The facility requires exemptions from certain requirements of 10 CFR Part 50 and 10 CFR Part 70. These include:
(a) an exemption from the requirements of 10 CFR 70.24 for the criticality alarm monitors around the fuel storage area; (b) an exemption from the requirement of 10 CFR Part 50, Appendix J - Option B, paragraph III.B, exempting the measured leakage rates from the main steam isolation valves from inclusion in the combined leak rate for local leak rate tests (Section 6.2.6 of SSER 6);
and (c) an exemption from the requirements of paragraph III.B of Option B of 10 CFR Part 50, Appendix J, exempting leakage from the valve packing and the body-to-bonnet seal of valve 1E51-F374 associated with containment penetration IMC-44 from inclusion in the combined leakage rate for penetrations and valves subject to Type B and C tests (SER supporting Amendment 62 to Facility Operating License No. NPF-62). The special circumstances regarding each exemption, except for Item (a) above, are identified in the referenced section of the safety evaluation report and the supplements thereto.
Amendment No.105
i
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i i
An exemption was previously granted pursuant to 10 CFR 70.24. The exemption was granted with NRC material license No. SNM-1886, issued s
November 27, 1985, and relieved IP from the requirement of having a criticality alarm system.
IP is hereby exempted from the criticality alarm system provision of 10 CFR 70.24 so far as this section applies to the storage of fuel assemblies held under this license.
l 1
These exemptions are authorized by law, will not present an undue risk j
to the pubile health and safety, and are consistent with the common defense and security. The exemptions in items (b) and (c) above are l
2 granted pursuant to 10 CFR 50.12. With these exemptions, the facility I
will operate, to the extent authorized herein, in conformity with the j
application, as amended, the provisions of the Act, and the rules and regulations of the Commission.
E.
The licensees shall fully implement and maintain in effect all provisions of the Commission-approved physical security plan, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled:
"Clinton Power Station Physical Security Plan,"
with revisions submitted through May 27, 1993; "Clinton Power Station Training and Qualification Plan," with revisions submitted through May 27, 1993; and "Clinton Power Station Safeguards Contingency Plan,"
with revisions submitted through May 27, 1993. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.
F.
IP shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report as amended, for the Clinton Power Station, Unit No. 1, and as approved in the Safety Evaluation Report (NUREG-0853) dated February 1982 and Supplement Nos. I thru 8 thereto subject to the following provision:
IP may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown-in the event of a fire.
G.
Except as otherwise provided in the Technical Specifications or Environmental Protection Plan, IP shall report any violations of the requirements contained in Section 2.C of this license in the following-manner:
initial notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC Operations Center via the Emergency Notification System with written followup within thirty days in accordance with the procedures described in 10 CFR 50.73(b), (c), and (e).
Amendment No. 105
Definitions 1.1 1.1 Definitions (continued)
EMERGENCY CORE COOLING The ECCS RESPONSE TIME shall be that time interval SYSTEM (ECCS) RESPONSE from when the monitored parameter exceeds its ECCS TIME initiation setpoint at tie channel sensor until the ECCS equipment is capable of performing its i
safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays, where applicable. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.
END OF CYCLE The EOC-RPT SYSTEM RESPONSE TIME shall be that RECIRCULATION PUMP TRIP time interval from initial movement of the (E0C-RPT) SYSTEM RESPONSE associated turbine stop valve or turbine TIME control valve to complete suppression of the electric arc between the fully open contacts of J
the recirculation pump circuit breaker.
The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.
l ISOLATION SYSTEM The ISOLATION SYSTEM RESPONSE TIME shall be that RESPONSE TIME time interval from when the monitored parameter exceeds its isolation initiation setpoint at the channel sensor until the isolation valves travel to their required positions.
The response time r:,ay be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.
(continued) f i
l CLINTON 1.0-3 Amendment No. 105
Primary Containment 3.6.1.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.1.1
NOTE-----------------
The results of SR 3.6.1.1.2 shall be included when evaluating compliance with this limit.
1 Perform required visual examinations and In accordance 1eakage rate testing, except for primary with the containment air lock testing, in Primary accordance with the Primary Containment Containment Leakage Rate Testing Program.
Leakage Rate Testing Program SR 3.6.1.1.2 Perform leakage rate testing of Primary In accordance Containment Hydrogen Recombiner System with the outside its containment isolation valves Primary at P,.
Containment Leakage Rate Testing Program CLINTON 3.6-2 Amendment No. 105
Pritary Containment Air Locks 3.6.1.2 SURVEILLANCE REQUIRENENTS SURVEILLANCE FREQUENCY SR 3.6.1.2.1
NOTES------------------
1.
Only required to be met during MODES 1, 2, and 3.
2.
An inoperable air lock door does not invalidate the previous successful performance of the overall air lock leakage test.
3.
Results shall be evaluated against acceptance criteria applicable to SR 3.6.1.1.1.
Perform required primary containment air In accordance lock leakage rate testing in accordance with the with the Primary Containment Leakage Rate Primary Testing Program.
Containment Leakage Rate Testing Program SR 3.6.1.2.2
NOTE-------------------
Only required to be performed upon entry or exit through the primary containment air lock.
Verify on1.i one door in the primary 184 days containment air lock can be opened at a time.
l l
CLlNTON 3.6-8 Amendment No. 105 l
PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued) i SURVEILLANCE FREQUENCY SR 3.6.1.3.4 Verify the isolation time of each power In accordance operated and each automatic PCIV, except with the MSIVs, is within limits.
Inservice Testing Program SR 3.6.1.3.5
NOTE------------------
Only required to be met in MODES 1, 2, and 3.
Perform leakage rate testing for each Once within 92 primary containment purge valve with days after
)
resilient seals.
opening the valve afiQ In accordance with the Primary Containment Leakage Rate Testing Program SR 3.6.1.3.6 Verify the isolation time of each MSIV In accordance is 2 3 seconds and s 5 seconds.
with the Inservice Testing Program SR 3.6.1.3.7 Verify each automatic PCIV actuates to 18 months the isolation position on an actual or simulated isolation signal.
(continued)
CLINTON 3.6-17 Amendment No. 105
PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.6.1.3.8
NOTE------------------
Only required to be met in MODES 1, 2, and 3.
Verify the combined leakage rate for all In accordance secondary containment bypass leakage with the paths is s 0.08 L, when pressurized to Primary 2 p,.
Containment Leakage Rate Testing Program SR 3.6.1.3.9
NOTE------------------
Only required to be met in MODES i, 2, and 3.
Verify leakage rate through each main In accordance steam line is s 28 scfh when tested at with the 2 P,.
Primary Containment Leakage Rate Testing Program SR 3.6.1.3.10
NOTE------------------
Only required to be met in MODES 1, 2, and 3.
Verify combined leakage rate through In accordance hydrostatically tested lines that with the penetrate the primary containment is Primary within limits.
Containment Leakage Rate Testing Program (continued)
CLINTON 3.6-18 Amendment No. 105
Prograns and Manuals 5.5 5.5 Programs and Manuals (continued)
)
5.5.11 Technical Soecifications (TS) Bases Control Procram This program provides a means for processing changes to the Bases of these Technical Specifications.
a.
Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.
b.
Licensees may make changes to Bases without prior NRC approval provided the changes do not involve either of the following:
1.
A change in the TS incorporated in the license; or 2.
A change to the USAR or Bases that involves an unreviewed safety question as defined in 10 CFR 50.59.
The Bases Control Program shall contain provisions to ensure c.
that the Bases are maintained consistent with the USAR.
d.
Proposed changes that meet the criteria of either Specification 5.5.11.b.1 or Specification 5.5.11.b.2 above shall be reviewed and approved by the NRC prior to implementation. Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).
5.5.12 Ultimate Heat Sink (VHS) Erosion. Sediment Monitorina. and Dredaina Proaram A program to provide maintenance on the UHS in the event inspections of the UHS dam, its abutments, or the UHS shoreline indicate erosion or local instability.
This program shall ensure that the UHS is maintained in such a way as to achieve the following objectives:
a.
During normal operation, there will be a volume of water in the UHS below elevation 675 sufficient to receive the sediment load from a once-in-25-year flood event; and b.
Still be adequate to maintain the plant in a safe-shutdown condition for 30 days under meteorological conditions of the severity suggested by Regulatory Guide 1.27.
I (continued)
CLINTON 5.0-16 Amendment No. 105
i Progra2s and Manuals I
5.5 i
5.5 Programs and Manuals (continued) 5.5.13 Primary Containment Leakaae Rate Testina Proaram A program shall be established to implement the leakage rate testing of the primary containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions.
This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, " Performance-Based Containment Leak-Test Program," dated September 1995, except that 4
Bechtel Topical Report BN-TOP-1 is also an acceptable option for performance of Type A tests.
The peak calculated containment internal pressure for the design basis loss of coolant accident, P,, is 9.0 psig.
i The maximum allowable primary containment leakage rate, L,, at P,,
shall be 0.65% of primary containment air weight per day 1
i Leakage Rate acceptance criteria are:
a.
Primary containment leakage rate acceptance criterion is s 1.0 L,.
During the first unit startup following testing in accordance with this program, the leakage rate acceptance i
criteria are s 0.60 L for the Type B and Type C tests and s0.75L,forTypeAfests; b.
Air lock testing acceptance criteria are:
1)
Overall air lock leakage rate is s 5 scfh when tested at 2 P,,
2)
For each door, leakage rate is s 5 scfh when the gap between door seals is pressurized to 2 P,.
The provisions of SR 3.0.2 do not apply to the test frequencies specified in the Primary Containment Leakage Rate Testing Program.
The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.
CLINTON 5.0-16a Amendment No. 105 l
.