ML20101A869
| ML20101A869 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 04/24/1992 |
| From: | Hannon J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20101A872 | List: |
| References | |
| NUDOCS 9205010082 | |
| Download: ML20101A869 (8) | |
Text
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9 40u9'o 9
UNITED STATES
- g NUCLEAR REGULATORY COMMISSION n
WASHINGTON, D. C 20555 e
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ILLIN0IS POWER COMPANY. ET IL DOCKET NO. 50-461 CLINTON POWER STATION. UNIT 'tl0.1 AMENDMENT TO FACILITY OPERATINyi LICENSE Amendment No. 62 License No. NPF-62 1.
The Nuclear Regulatory Consnission (the Commission) has found that:
A.
The application for amendment by I*,linois Power Company * (IP), and Soyland Power Cooperative, Inc. (the licensees) dated December 23, 1991, complies with the standardt, and requirements of the Atomic Energy Act of 1954, as amended (tha Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the aapl cation, the provisions of the Act, and :.1e rules and 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 con-ducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense ard sece-ity or co the health and safety of the public; and E.
The issuante of this amendmera is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, Facility Operating License No. NPF-62 is hereby amended by changes to the Technical Specifications as indicated in the attachment to thu. license amendment, and paragetphs 2.C.(2) and 2.0 to read as follows:
- Illinois Power Company is authorized to act as agent for Soyland Power Cooperativo, Inc. and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.
9205010082 920424 PDR r*
ADOCK 05000461 PDR
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2 (2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix 8, as revised through Amendment No.
62, are hereby incorporated into this license.
Illinois Power Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
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 70.2' for the criticality alarm monitors around the fuel storate area: ta; '
exemption from the requirements of Appendix A to 10 CFR Part ;0 aeral Design Criterion 61 to permit a schedu! - da'irral cf
-mpletion of preoperational testing of a portion of the fue Handling System until prior to offloading fuel from the reactor vessel (Section 14 SSER 8); (c) an exemption from the requirement of paragraph III.D.2(b)(ii) of Appendix J, substituting tiie seal leakage test at Pa e' paragraph III.D.2(b)(iii) for the entire air?cck test at Pa of paragraph III.D.2(b)(ii) of Appendix J when no maintenance has been performed in the airlock that could affect its sealing capability (Section 6.2.6 of SSER 6); (d) an exemption from the requirement of paragraph III.C.3 of Appendix J, exempting the measured leakage rates from the main steam isolation valves from inclusion in the combined leak rate for the local leak rate tests (Section 6.2.6 of SSER 6); and (e) an exemption from the requirements of paragraph III.B.3 of Appendix J, exempting leakage from the valve packing and the body-to-bonnet seal of valve IE51-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.
The special circumstances regarding each exemption, except for Items (a) and (e) above, are identified in the referenced section of the safety evaluation report and the supplements thereto.
An exemption was previously granted pursuant to 10 CF9 70.24.
The exemption was granted with NRC materials license No. 3NM-1886, issued November 27, 1985, and relieved IP from the quirement of having a criticality alarm system.
IP is hereby em -pted from tho criticality alarm system provision of 10 CFR-70.24 so far asithis section applies to the storage of fuel assemblies held under this license.
The special circumstances-regarding the exemption identified in L
Item (e) above are identified in the shfety evaluation accompanying Amendment No. 62 to this license.
These exemptions are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. The exemptions in items (b), (c) and (d) above are granted pursuant to 10 CFR 50.12.
With these
3 exemptions, the facility will operate, to the extent authorized herein, in conformity witl. application, as amended, the provision of the Act, and the rules and regulations of the Commission.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/
/ e~7/
John N. Hannon, Dinector Project Directorate 111-3 Division of Reactor Projects Ill/IV/V ffice of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
April 24, 1992 8
)
ATTACHMENT TO LICENSE AMENEMENT N0. 62 FACILITY OPERATING LICENSE NO. NPF-62 DOCKET NO. 50-461 Replace the following pages of the licensee and Appendix "A" Technical Specifications with the attached pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf pages are provided to maintain document completeness.
Remoye 1.0_s_qr_t 5 (license) 5 (license) 6 (license) 6 (license) 3/4 6-4 3/4 6-4
(8) Post-Fuel Loading Initial Test Program (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) Emergency Response Capabilities (Generic Letter 82-33, Supplement 1
.to NUREG-0737, Section 7.5.3.1, SSER 5 and SSER 8, and Section 18, SER, SSER S and Safety Evaluation Dated April 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 f1nal supple-mental summary report within 90 days of issuance of the full power license that completes all the remaining items identified in Sectioi 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 requirements of Appendix A to 10 CFR Part 50, General Design Criterion 61 to permit a schedular deferral of completion of preoperational testing of a portion of the Fuel Handling System until prior to offloading fuel from the reactor vessel
-(Section 14, SSER 8); (c) a, exemption from the requirement of paragraph III.D.2(b)(ii) of Appendix J, substituting the seal leakage test at Pa of paragraph III.D.2(b)(iii) for the entire airlock test at Pa of paragraph III.D.2(b)(ii) of Appendix J when no maintenance has been performed in the airlock that could affect its sealing capabMity (Section 6.2.6 of SSER 6);
[
(d) an exemption from the requirement of paragraph III.C.3 of Appendix J.
exempting the measured leakage rates from the main. steam isolation valves from inclusion in the combined leak rate for the local leak rate tests (Section 6.2.6 of SSER 6); and (e) an exemption from the requirements of paragraph III.B.3 of Appendix J, exempting leakage from the valve packing and the body-to-bonnet seal of valve lE51-F374 associated with containment penetration 1MC-44 from inclusion in the-combined leakage rate for penetra-tions and valves subjeci. to Type B and C tests. The special circumstances regarding each exemption, except for Items (a) ard (e) above, are identified in the referenced section of the safety evaluation report and the supple-ments thereto.
i Amendment No. JB, 62
1 i
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 from the requirement of having a criticality alann system.
IP is hereby exempted from the criticality alarTn system provision of 10 CFR 70.24 so far as this section applies to the storage of fuel assemblies held under this license.
The special circumstances regarding the exemption identified in Item (e) above are identified in the safety evaluation accompanying Amendment No. 62 to this license.
These exemptions are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security.
The exemotions in items (b), (c) and (d) above are granted pursuant to 10 CFR 50.12.
With these exemptions, the facility will operate, to the extent authorized herein, in con-formity with the application, as amenaed, the provisions of the Act, and the rules and regulations of the Commission.
E.
The licensees shall fully implement and maintain in effect all provi-sions of the Commission-approved physical security plan, guard training and qualification, and safeguards contirgency 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 November 30, 1987; "Clinton Power Station Training and Qualification Plan," with revisions submitted through October 1,1987; and "Clinton Power Station Safeguards Contingency Plan,"
with revisions submitted through Octcber 1,1987.
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 apprnved fire protection program as described in 1.1e 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 saall report any violations of the requirements contained in Section 2.C of tnis 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 Energency Notification System with written followup within thirty days in accordance with the procedures described in 10 CFR 50.73(b), (c), and (e).
Amendment flo. 3,. 62 l
. - - - _ - _ ~.
7 CONTAINMENT SYSTEMSc y
~
PRIMARY CONTAINMENT LEAKAGE.
LIMITING CONDITION FOR OPERATION (Continued) 53.6.1.2 ACTION (Continued):
' The overall integrated leakage rate (s) to less than or equal to 0.75 La, a,
and b.
The combined leakage rate for a'il penetrations and all valves subject to Type B and C tests to less than or equal to 0.60 La, and The leakage rate to less-than 28 scf per hour for any one main steam line c.
through the isolation valves, and d.
- The combined -leakage rate for all penetrations shown in Table 3.6.4-1 as secondary containment bypass-leakage paths to less than or equal to 0.08 La, and The_ combined leakage rate for all containment isolation valves in hydro-e.-
statically tested lines per Table 3.6.4-1 which penetrate the primary con-
.taintnentlto less than or equal to 1 gpm times the total number of such valves prior-to increading reactor coolant system temperature above 200'F.
s F[
SURVEILLANCE REQUIREMENTS
- 4. 6; 1,2 The~ containment 1eakage rates shall be demonstrated at the following test' schedule and shall be determined in conformance with the criteria speci-fied in Appendix J of 10 CFR 50 using the methods and provisions of ANSI.
N45.4-1972 and BN-TOP-1 and verifying the_ result by the Mass Point Metho--
dology described'in-ANSI /ANS N56.8-1981=
Three Type:A Overall-Integrated Containment Leakage Rate. tests shall be-a..
conducted at-40 t 10_ month intervals during shutdown at Pa, 9.0:psig-
~
- during each 10 year service-period. The third test of each set shall be conducted during the' shutdown for_the-10 year plant inservice inspection.-
- b.-
-If.any periodic Type A test fails to meet 0.75 La the-test schedule for
~
subsequent Type A tests shall-be reviewed and approved by the Commission.-
- If two consecutive Type A tests fail to meet C.-75 La_a Type A test shall
'be performe_d at least every 18' months until two consecutive Type A tests meet 0.75 La at which time the above test schedule may be resumed.
t The accuracy of each Type A test.shall be verified by a supplemental test c.
which:
1.
Confirms the accuracy of-the test by verifying that the difference
-between the supplemental-data and the Type A test data is within 0.-25 La. -The formula to be used is :
[Lo +' Lam - 0.25 La] < Lc <-
~
[Lo + Lam + 0.25 La]'where Lc = supplemental' test result, Lo~=
-superimposed leakage and Lam = measured Type A leakage.
Cl.INTON - UNIT 1 3/4 6-3 l
+
-CONTAINMENT SYSTEMS' PRIMARY CONTA1'HENT LEAKAGE SURVEILLANCE REQUIREMENTS-(Continued) 4.6.1.2 -(Continued) 2.
Has duration sufficient to establish accurately the chenge in leakage rate between tne Type A tcst and the supplemental test.
3.
Requires the quantity of gas injected into the primary containment or bled from the primary containment during the supplemental test to be between 0.75 La and 1.25-La.
d.
Type 8 and C tests shall be conducted *** with gas at Pa, 9.0 psig*, at inter-l vals no greater than 24 months except for tests involving:**
1.
Air locks, 2.
Main steam line isolation valves, 3.
Penetrations using continuous leakage monitoring systems, 4.
All containment-isolation valves in hydrostatically tested lines per
'. Table _3.6.4-1 which penetrate the primary containment, and 5.
Purge supply and exhaust isolation valves with resilient material
-seals.
e.
Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1.3.
f.
Main steem line isolation valves shall be leak tested at least once per 18 months.
g.
Type B tests for penetrations employing a continuous leakage monitoring system shall be conducted at Pa, 9_.0 psig, at every other reactor shutdown for refueling, but in:no-case'at intervals no greater than once per 3 years.
h.
.All containment isolation valves in-hydrostatically tested lines per Table 3.6.4-1 which penetrate the primary containment shall be-leak tested at
'least once per 18 months.
i.
Purge supply-and exhaust isolation valves with resilient material seals L
shall be tested and demonstrated OPERABLE per Surveillance Require-ment 4.6.1.8.3.
I L
j.
The provisions of Specification 4.0.2-are not applicable to Specifica-tions 4.6.1.2.a, 4.6.1.2.b, 4.6.1.2.d.-and 4.6.1.2.g.
i' L
"Unless a hydrostatic test is required per Table 3.6.4-1.
l
- Except asiprovided in NRC-approved exemption to Appendix J to 10 CFR 50 for containment penetration IMC-44 CLINTON
. UNIT 1 3/4 6 Amendment No. J*62