ML20115G118
| ML20115G118 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 10/16/1992 |
| From: | ILLINOIS POWER CO. |
| To: | |
| Shared Package | |
| ML20115G107 | List: |
| References | |
| NUDOCS 9210260027 | |
| Download: ML20115G118 (9) | |
Text
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Attachment 2 to U-602041 LS-92-013 l (8) Post-Fuel Loadirg Initial Test Program (Section 14, SER, SSER S and SSER 6)
Any changes to the initial test program described in Section 14 of the FSAR rude in accor Jance with the provisions of 10 CFR S0.59 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.S.3.7, SSER S_ and SSER 8, and _Sec*gn 18, SER, SSER S and Safety Evaluation Dated April 17, 1987) . .
- a. IP in accordance with the t.oualtment contained in a letter dated December 11, 1986, shall install and have operational' separate power sources for caca 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 desiga final supple-mental sumnary 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)anexemptfionfromthe
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requiremnts ~of 10 CFR,70.24 for the criticality alarm. monitors around the fuel storage area; (b) an eke ptied-frc- th: requgr=cht: Of Appendix ^.
te-10-CFR Part40r-Gener44-Design Criteri0n 51 te pemit a chedular . !
4eferral of c^=pletion ef-preepenticn:1 tecti ~; cf a p^rtica ef-the Feel-
-Haa4 Mag Sy: tem-unt41-prisetc effle: ding fucl frc; the rceter ve: 01-
@ JSection " SSEP h(4) an exemption from the requirement of paragraph
- II.D.2(b)(11) of App 6ndix 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(bpi) of Appendix J when no maintenance has been performed in the airlock the.t could affect its sealing capability (Section 6.2.6 of SSER 6);
J4). an exemption from the requirement of paragraph III.C.3 of Appendix J. l exempting the measured leala.cc rates from the main steam isolation valves from inclusion in :te combin.:d leak rate for the local' leak rate'. tests (Section 6.2.6 of SSER 6); ant.(e+ . n exemption from the requirements of jg l
paragraph III.e.3 of_ Appendix J. e> ' ting leckage from the valve packing and the body-to-bonnet seal of valw IE51-F374 associated with containment penetration 1MC-44 from inclusion in the combined leakage rate for penetra-tions and valves subject to Type B and C tests. The special circumstances' regarding each exemption, except for Items (a) and above, are identified in the referenced section of the safety evaluation eport and the supple-ments thereto.
.w(cb 9210260027 921016 i i
PDR ADOCK 05000461 P POR
, Attachment 2 to U-602041 LS-92-013 Page 6 of 13 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 r.riticality alann system. IP is-hereby exempted from the criticality alann system provision of 10 CFR 70.24 so far as this section applies to the storage of fuel assemblies held under this license, t special circumstances regarding the exemption identified in (cl) Ite.A(+). above are identified in the safety evaluation accompanying l Amendment No. 62 to this license.
I These exemptions are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the comon defense and securi,ty. The exemptions in itus (b)K(c) 6n~@.(4).
above are granted pursuant to 10 CFR 50.12. With these exemptions, the facility will . operate, to the extent authorized herein, in con-
. fonnity with the application, as amended, the provisions of the Act, a id the rules and regulations of the Comitsion.
E. The licensees shall fully implement and maintain in effect all provi-sions of the Commission-approved physical security plan, gun d training and qualification, and safeguards contingency plans including amendments
, made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revistors 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 centain Safeguards Infonnation protected under 10 CFR 73.21, are entitled: "Clinton Power Station Physical Security Plan," with
, revisions submitted through November 30,1987; "Clinton Power Station 1 raining and Qualification Plan," with revisions submitted through October 1,1987; and "Clinton Pcwe' Station Safeguards Contingency Pla~n,"
with revisions submitted through + .ar 1,1987. Changes made in
, accordance with TO CFR 73.55 shall be impl:;nented in accordance with
! the schedule set forth f: erein.
F. IP shall implenent and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysi., Report as amended, for the Clinton Power Station, Unit No.1, and as approved in th Safety Evaluation Report (HUREG-0853) dated February 1982 and Supplement Nos.1 thru 8 thereto subject l
to the following provision:
IP may make changes to the approved fire protectici program l without prior approval of the Commission only if tnose changes I would not adversely affect the ability to achieve and maintain t safe shutdown in the event of a fire.
G. Except as otherwise provided in the Technical Specifications or Environmertal Protection Plan, IP shall report any violations of the
, requirements contained in Section 2.C of this license in the folbin9 l 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 l NRC Operations Center via the Emergency Notification System with l written followup within thirty days in accordance with the procedures described in 10 CFR 50.73ib), (c), and (e).
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Attachment 2 to U-602041 LS-92-013 EMERGENCY C0_R,E_C000 NG SYSTEMS Page 7 of 13 3/4.5.2 ECCS - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.5.2 At least two of the following shall be OPERABLE and capable of being l
powered from a diesel generator of Specification 3.8.1.2.b.
- a. The low pressure core spray (LPCS) system with a flow path capable of l
taking suction from the suppression pool and transferring the water I through the spray sparger to the reactor vessel.
1
- b. Low pressure coolant injection (LPCI) subsystem "A" of the RHR system with '
a flow path capable of taking suction from the suppression pool and trans '
, ferring the water to the reactor vessel, i i
l
! c. Low pressure coolant injection (!PCI) subsystem "B" of the RHR system with
! a flow path capable of taking suction frou the suppression pool and trans-ferring the waler to tha reactor vessel. i 1
, d. Low pressure coolant injection (LPCI) suosystem "C" of the RHR system with a flow path capable of taking suction from the suppression pool and trans-ferring the water to the reactor vesstl. 1
- e. The high pressure core spray (HPCS) system with a flow path capable of taking suction from one of the following water sources and trar.sferrir.9 the water through the spray sparger to the reactor vessel:
- 1. From the supp:ession pool, or ,
- 2. When the suppression pool it. vel is less than the limit or is drained, '
from the RCIC st r tank containino at 1 125J00 available gallons of wate ,alent te e ! Bel c. 9EL l v
APPLICABILITY: OPERATIONAL CONDITIONS 4 and 5^.
ACTION:
- a. With one of the above required subsystems / systems inoperable, restore at least two cubsystems/ systems to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or suspend all operations that have a potential for draining the reactor vessel. The provisions of Specification 3.0.4 are not applicable.
- b. With both of the above required subsystems / systems inoperable, suspend CORE ALTERATIONS and all operations that hta a potential for draining-the reactor vessel. Restore at least one subsystem / system to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or establish PRIMARY CONTAINMENT INTEGRITY within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
is removed, '.he cavity is flooded, the reactor cavity to steam dryer pool j gate is open and water level in these upper containment pools is maintained
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within the limits of Specification 3.9.8 and 3.9.9.
CLINTON - UNIT 1 3/4 5-5
Attschment 2
^
.to U-6a*U41
- LS-92-015 Page 8 or 13 EMERGENCYCOREC00i!NGSYSTEMS .
I 3/4.5.3 SUPPRESSION POOL LIMITI,4G CONDITION FOR OPERATION l
3.5.3 The suppression pool shall be OPERABLE: ,
- a. In OPERAT' JAL CONDITIONS 1, 2, and 3 with a containeo n ter volume of at least 146,400 ft 3, equivalent to a level of 18'11".
- b. In OPERATIONAL CONDITIONS 4 and 5* with a contained water volume of at least 98,700 f t3 , equivalent to a level of '12'8", except that the suppres-sion pool leml may be less than the limit or may be drained provided t :.t:
- 1. No operations are performed that have a potential for draining the reactor vessel,
- 2. The reactor mode. mtch is locked in:the Shutdown or Refuel position,
- 3. The RCIC storage tank contains at 'le 125,000 available gallons i ro" rnd of water,Qent tefleve} c
- 4. The HPCS system is OPERABLE per Specification 3.5.2 with an OPERASLE flow path capable of taking suction from the RCIC storage tank and transferring the water through the spray sparger to the reactor vessel.
- APPLICAb kITY: OPERATIONAL CONDITIONS 1, 2, 3, 4, and 5*.
ACTION:
- a. In OPERATIONAL CONDITION 1, 2, or 3 with the suppression pool water it.el less than the above limit, restore the water level to within the limit L within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT SHUTDOWN withi.) 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 SHUT 00VN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
I b. In OPERATIONAL CONDITION ar 5* with the suppression pool water level less than the above limit or drained and the above required conditions -i not satisfied, suspend CORE ALTERATIONS and all operations that have a potential for. draining the reactor vessel and lock the. reactor mcde switch in the %utdown position. Establish SECONDARY CONTAINMENT INTEGRITY with in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
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l "The suppression pool is not required to be OPERAdLE provided that tha reactor vessel head is remcved, the cavity is flooded, the reactor cavity to, steam dryer pool gate is open, and the water level in these upper containment. pools is maintained within the limits of Specificatior,s 3.9.8 anc' 3.9.9.
4 Ct.INTON - UNIT 1 3/4 5-7 i
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-Y Y' Attachm2nt 2 6 E O* D Vi d f.d h v" CMbby C6 .
l' age 9 of 13 A A s ELECIRIU.L POWER SYSTEMS
' 015TRIBUT10N - SHUTDOWN L1HITING CONDITION FOR OPEPATION ~ .
3.8.3.2 As a minimum, the following power distribution s.vstem divisions shall be' energized:
- a. For AC power distribution, Div'ision I or Division II, ar..i when the HPCS system is required to be OPERABLE, Division III and Division IV, with: ,
- 1. Division I consisting of:
a) 4160-volt AC Bus 1A1.
b) 480-volt Unit Substations A and 1A.
- 1) Aux. Bldg. MCCs 1A1, 1A2, IA3, IA4.
- 3) D.G. MCC 1A. ~
- 4) Control Bldg. MCCs El, E2, and G
- 5) Damper HCC A ;
d) 120-volt AC distribution panels in Auxiliary Building 480-volt MCC 1A1 and Control , Building MCC E2.
e) 120-volt AC uninteriuptible distribution panels energized from 1C71-5001A, which is fed from Control Building MCC E2 and from Auxiliary Building 480-volt MCC 1A1 through 125-volt DC HCC 10C13E. .
- 2. Division 11 consisting of; .
a) 4160-volt AC Bus 181. ,
b) 480-volt Unit Substations B and 18, c) 480-volt AC HCCs 1). Aux. Bldg. MCCs 181, 182, 183, 184
- 2) 5SW HCC 18 '
- 3) 0.G. MCC IB
- 4) Control Bldg. MCC F1, f2, and H ,
- 5) -Damper HCC B d) 120-volt AC distribution panels =in Auxiliary Building 480-volt
e) 120-volt AC uninterruptible distribution panels energized from-IC71-50018, which is fed from Control' Building MCC F2 and from Auxiliary Building 480-volt MCC IB1 thrr agh Ira-volt,0C HCC 10C14E.
CLINTON - UNIT 1 .
3/4 6-21
Attachment 2 to U-f>02041 LS-92-013 Page 10 of 13 J.
. ELEC1RICAL POW R SYSTEMS 0151RIBUT10H - SHulDOWN LIMITING CONDITION FOR OPERAT10N (Continued) 3.8.3.2 (Contir.ued)
- 3. Division III' consisting of:
a) 41f>0-volt AC Bus '.C1.
b) Auxiliary Building 480-volt MCC 1C and Auxiliary Building 480-volt MCC 1C1, and SSV HCC IC.
. c) 120-volt AC distrib'ution panels in Auxiliary Building 480-volt MCC IC and Auxiliary Building MCC IC1.
d) 120-volt AC uninterruptible distribution panels energized from IC71-5001C, which is fed from Auxiliary Build 480-volt MCC IC and 125-volt DC Distribution Panel 1E22-5001C.
- 4. Division IV consisting of 120-volt AC Uninterruptible distribut 'on panel energized from IC71-5001D, which is fed from Auxiliary Building 400-volt MCC-181 and 125-volt DC HCC 10C15E.
- b. For DC power distribution, Division I or Division II, end when the HPCS q system is required to be OPERABLE, Division III, and Division IV, with:
- 1. Division I consisting of 125-volt DC Batteries 1A,125-volt Battery Charger 1A, 125-volt DC HCC-1A, and distribution panel.
- 2. Division 11 consisting of 125-volt DC Batteries 1B,125-volt Battery-Charger 1B,125-volt DC HCC-18, and distribution panel. ~
Charger IC and distribution panel.
- 4. Division IV consisting of 125-volt DC Battery 10,125-volt Battery Charger 10,125-volt DC HCC-10, and distribution panel.
APPLICABILITY: OPERATIONAL C)NDITIONS 4, 5, and *.
ACTION:
- a. for AC power distribution:
- 1. With both Division I and Division II of the above requir d AC dis-tribution system not energized, suspend CORE ALTERATIONS, handling of irradiated fuel in the secondary containment and operations with a pcttntial for draining the reactor vessel.
- When handling irradiated fuel in the secondary containment.
CLINTON - UNIT 1 3/4 8-22
Attachment 2
. . to U-602041 LS-92-013 Page 11 of 13 REFUELIliG OPERATIOl15 3/4.9.12 li1CLIllED FUEL TRAftSFER LY_ STEM LIMITIt1G C0tt0lTIO!4 FOR OPERATION 3.9.12 The inclined fuel transfer system (IFTS) may be in ope ation provided that:
- a. The access, doors
- of all rooms through which the transfer system penetrates are closed and locked.
- b. All access door
- interlocks are OPERABLE.
- c. The blockint valve located in the fuel building IFTS hydraulic power unit --
is OPERABLE.
- c. At least one IFTS carriage position indicator is OPERABLE . each carriage position and at least one liquid level sensor is OPER'.BLE.** 4L
- e. Any keylock switch that provides IFTS access contro,1-transfer system lock-at is OPERABLE.
APh 'lITY: When the IFTS containment blank flange is removed.
ACTION:
With the requirements of the above specification not satisfied, suspend IFTS operation with the IFTS at r.ither terminal peint. Tho provisions of Specifi-cation 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.12.1 Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> prior to the startup 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 /> during operation of the IFTS, verify that no personnel are in are:s imaediately
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adjacent to the IFTS and that all access doors
- to rooms through which the-IFTS penetrates are cicsed ana locked.
4.9.32.2 Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to the operation of IFTS 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 /> thereaf ter, verify that at least one IFTS carriage position indicator is OPERABLE each carriage position and at least one liquid level indicator is OPERABLE.
' ^^
" Includes y movable shie V -
[ '*The biccking vahc ;.. thc fucl building IFTS hydraulic pcuct uni-t-and the liqm d level indkator ar : not required t0 bc OPEP^.BLE fer the purposec of the: :pcci ficaticas prier tc 0'!cading '":wiinted 'uc! ' rem the mact-
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.M A, _
CLI JTON - NIT 1 3/4 9-1S
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_ Attachment 2
. REFUELIllG uPERATIONS- to U-602041 LS-92-013 INCLINED FUEL TPANSFER.' SYSTEM I> age 12 of 13.
SURVFILLMICE REQUIREMENTS (Continued) H 4.9.12.3 Within 4 hoort prior to tne operation of the IFTS and at least once
. per 7 days thereaf ter, verify that.
- a. All access door" interlocks are OPERABLE.
. )
- b. The blockiig valve in the fuel Building IFTS hydraulic power unit is 1 l
OPERABLE. *
- c. The keylock switches which provide IFTS access or control-transfer system lockout are OPERABLE. i q
j
.j I
- )
i l
i i
l i- -
1
.i I F
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- ~
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[.
lude- removable shields. f
- Thc alecking- valvc - in thc Tucl %'? ding IFT5 hydrauli: p=c ; unit cod the l# quid -leve! .ndic+4.er are aet-r-cquired to be- OPER?SLt fcr the purpc w-ef-
- thece speci'icatienc pricr to c'flecding irradictcd fucl f rein thc rccctcr-6e4, t _+
A h '
CLINTON - UNIT 1 3/4 9-20 i,
l w n- e e ~ r ~- s
- r
Attachment 2 A
to U-602041 '
LS-k!-013
- Page 13 of 13 ADMINISTRATIVE CONTROLS under the administrative contr61 of the Shif t Supervisor on duty and/or the Radiation Protection Supervisor. Doors shall remain locked except during periods cf access by personnel under an approved RWP.". For individual areas accessible 'o persorinel with rehtion levels such that a major porcion of the body could receive in 1 hout a dose in excess of 1000 mrem"^ that are located within large areas, such as the containment, where no anclosure -
exists for purposes of 'ocking, and no aclosure can be reasonably constructed around the individual areas, then that crea shall be roped cff, conspicuously '
posted, and a flashing light shall be activated as a warning device.
6.12.3 In addition to the requirements of Specifications 6.12.1 and 6.12.2, for individual areas accessible to personnel such that a major o tion of the body could receive in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> a dose in 4xcess of 3000 mrem entry shall l require an approved RWP which will specify dose. rate levels in the immediate work area and require that stay tin.es .shall be estauliched.
In lieu of the stay time specification of the RWP, continuous surveillance, direct or remote (such as use of closed circuit TV cameras), may be made by personnel qualifiad in radiation protection procedures to provide positive 1xposure control over the activities within the area. .
6.13 PROCESS CONTROL PROGRAM (PCP)
Changes to the PCP: .
- a. Shall be documented and records of reviews performed shall be
- retained as required by Specification 6.10.3.n. This documentation L shall contain:
l 1. Sufficient information to support the change together with the l appropriate analyses or evaluations, justifying the change (s), and
- 2. A determi Aion that the change will maintain the overall conformance of the solidified waste product to existing l
requirements of Federal, State, or other applicable regulations.
I
- b. Shall become effective ~after review and acceptance by the FRG and the approval of the Manager - Clin on Power Statica.
" Radiation protection personnel or personnel escorted by radiation protection personnel shall be exempt from the RWP issuance requirement for fields of l
less than 3000 mrem per nour during the performance of their assigr.ed radia-I tion protection duties, provided they are otherwise following plant radiation protection procedures for entry into high radiation areas.
- Measurements u de at 18 ..ches 'rca sources of radioactivity.
I CLINTON - ' UNIT 1 6-M L
l a