ML20094L054
| ML20094L054 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 03/09/1992 |
| From: | Tuckman M DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9203240235 | |
| Download: ML20094L054 (13) | |
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- March 9,1992 U.S. Nuclear Repl7 tory Commission Attention: Document Control De:k
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Wechington, D.C. 20555
Subject:
Catawba Nuclear Station Docket No. 50-413 -414 Selec.ed Licensee Commitments Manual (SLC)
Gentlemen:
Putsuant to 10 CFR 59.4 and 50.71, please find attached 10 copies of the latest revisions to the Catawba Selected Licensee Commitments Manual. The SLC Manual is Chapter 16.0 to the Catawba FSAR. This manual is meant to contaia commitments and other station issues that we Mieve warrant higher control, but are not appropnate in the Technical Specifications (TS). Instead of being updated with the annual FSAR Update, q
the SLC Manual will be updated monthly as necded during the year.
Very truly yours, C
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M.S. Tuckman HAF/haf Attachment e
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S. D. Ebneter Regional Administrator, Region II R. E.- Martin. ONRR W. T. Orders, Catawba Senior Desident Inspecto;
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DU(2 POWER March 5, 1992 Ret Catawba Nuclear Station Selected Licensee commitments j
Attached are revisions to the Catawba Nuclear Station Selected Licensee Commitment (SLC) Manual. This attachment consists of:
4 recently approved revisions to SLC 16.9-6, typographically corrected.pages froru SLCs 16.5-1 and 16.9-5, and the last page of SLC 16.9-5 which was inadvertently omitted in the last revision.
Your manual should be updated as follows:
EqplsLGMhese parica Insprt.Thgan_EAgne LOEP 1,2,'3 LOEP 1,2,3
-16.9-14b 16.9-14b, 15.9-14e 16.0-15, 16, 17 16.9-15, 16, 17
, 16.5-1, 2,7 3 16.5-1, 2, 3
Any questions should be directed to me at 704-373-2365.
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- Laura-Durba Nuclear Licensing Services
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4-DUKE -- POWER COMPAt1Y-
-CATAWBA NUCLEAR STATION
-SELECTED LICENSSE COMMITMENTS MAtCJAL
. LIST OF EFFECTIVE PAGES Page Revision _ Date
-LOEP 1 11/91 LOEP 2 02/92 LOEP.3 02/91 Tab 16.0 16.0-F 12/90 Tab 1E[1
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l16,1-1
. Tab 16.2' 16.2-1 11/91 16.2-2 11/91
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.-16.2-3 11/91
' Tab'16.3;.
-16.3-l'-
11/91 16.3-2 11/91=
Table'16.3-1 11/01
-Tab 16.4
-Tab-16.5
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=16.5-2 11/91'
'16.5 11/91 ll Tab 16.'6J Tab =16.f
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Tab 16-'9 16.9-0 12/90 16.9-1 12/90 16.9-2 12/90 16;9-3 12/90 16.9-4 12/90 16.9 12/90 16.9-6 12/90 1 6. 9 7.
12/90
- 16'.9-8.
12/90-
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- 16'.9-9--
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- 16.~9-10 12/90 16.9-11 12/90
-16.9 12/90 16.9-13 10/91-16.9-14"
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16.9-16 02/92-16.9-17 l02/92-l Tabis116.9-3 1 of 5.
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4 Page Revisio.n Date
- Table 16.9-3 2 of 5 12/90 Table 16.v-3 3 of 5 12/90 Tablo 16.9-3 4 ef-5 12/90
- Table 16.9-3 5 of 5 12/90
~ Tab =16.10 16.10-1 07/91 16.10-2 02/91-T_ab - 16.1);
_ Tab 16.12 i
. Tab 16.13
. 16.13-O' 12/90.
16.13-1 12/90 Tab 16 14f
, Tab 16.15 Appendix
' Directive 13.1.5 Pages-1 through 7
- Directive 3.1.51 Attachment 1 1 of 1 Directive 3.1.5 Attachmenti :2 1 of l' Directive 3.1.5. Attachment 3-1.of 1 Directive'3.1.5 Attachment 4 1 of 1
. Directive-3.1.5 Attachment 5 1 of 1 4
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.Page 3 02/91-
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l CATAWBA NUCLEAR STATION CCWIITTED FIRE DOORS l
Door No.
Location ElgVatipA E liA
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AX500F 56, FF Elevatiqn 543+0 AX202 50-51, NU AX214A 54-55, FF-GG
-AX214B 58-59 FF-GG AX217D 52-5;. BB AX217F 51, AA-BB AX217G.
52-53, BB AX227D 54-55, MM-NN AX227E 59-60, MM-NN AX227F 59, FF-GG AX328A 56-57, EE AX228B 57-50, EE a
AX24u 57-58, QQ I
AX253A 63-64, NU AX260B 61-62, BB-CC AX260E 52, CC AX260E 62, AA-BB AX260G 61-62, BB-CC AX260H 61-62,-BB-CC AX516M 62, CC T527#1 52-43, PS-CC ElAvation 554+0 AX354A 55, DD-EE AX354B 59, DD-EE AX418 57, BB AX419 57, DD-EE L
AX420A 59, DD-3E AX421A 55, DD-EE-S102A 53-54, AA E10.Ya419.IL33.0. A L
AX302 41, CC-DD AX304 41, AA-BB l
AXJ06 73, DD-EE AX308 73, BB-CC l
16.9-14b 10/91 L
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b ELqyAtion 605+0 s17003 50-51, JJ-KK I
AX700D G3-64, KK AX701 50-51, JJ-KK f.
AX714B 63-64, JJ-KK AX714C 50-51, JJ-KK AX720 50-51, Hh'-JJ AX721 63-64, liH-JJ AX715A 63-64, JJ-KK lhlglgar Servico Water _P.11po structura AX662A ElRNati.RD 5.0.910 S1114 QA Vault r
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16.5 SEACTOR COOLANT SYSTEM liljl L@P OPERATlQN WITH Ir$AQIATED FUEL IRlliE_gQRE l i a.E. A COMMITMFNT Operations with Reactor Coolant (NC) system level less than or equal to 161, with fuel in the core shall be conducted under the following conditions:
1)
At least ono hot leg will be maintained with no S/G nozzle dam installed until the reactor vausel head has been removed.
2)
If R/G nozzle dams ara to be used, one hot leg dam and a hot or cold leg manway on the associated S/G shall remain out anytime the reactor vessel head 4s in place.
If a cold log manway is being used, then all cold leg nozzle dams munt be installed.
3)
Two independent trains of NC level instrNments are required.
Tnene instruments shall have independent transmitters and shall not include the NC System sightglass (NCLG-G450) or tygon tubing.
4)
Two core exit thermocouples shall be maintained operating with temporary high alarms set at 140 _F and monitored except as noted below:
Final disconnection of the last two core exit thermocouplen shall occur no sooner tnan two hours prior j
to reactor vessel head re aoval.
Reconnection of at least two thermocouplas within two hours after reinstalling the reactor vessel head.
The total time without thermocouple indication shall not exceed 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
5)
Three power sources shall be available as follows:
- wo off-site power sources and one D/G, or One off-site powcr source and two D/Gs.
6)
Two independent makeup paths of botated water shall be available. during each of the follcwing conditions:
a)
Reactor Coolant System-intact:
One Centrifugal Charging Pump (NV) as required per Technical Specifications 3.1.2.1 and 3.1.2.3.
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16.5-1 11/91
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One Safety Injection Pump (NI) having its breaker installed in its associated cubicle and a ficw path available from the FWST to the NC System.
b)
Reactor Coolant System cpan to Containment atmosphere via I
j a hct leg vent path:
Onsa Centrifugal Charging Pump (m!) es required per Technical Specifications 3.1.2.1 and 3.1.2.3.
One of the following gravity flowpaths:
FWST through ND-33 to the colc igs via N1-173 A i
and/or NI-1788.
FWCT through the ND suction lines to the' hotlegs.
FWST through ND-33 to the hotlegs via NI-183B.
NOTE:
The number of open coatainment penetrations is limited such that the penetrations can be closed within two hours of losing ND.
Containment Closure must be established.
Containment Closure 7) is verified by the performance of PT/1/(2)/A/4200/02C-I, a
Containment closure Verification, with penatrations not
-verified acceptable administrative 1y controlled per OP/0 O/A/6100/14, Penetration Control During Modes 5 and 6.
g 8)
The reactor has been subcritical for at least 7 days; or Design Engineering has provided a required subcritical time based on plant operating history and actual reduced NCS level.
g AD_PLICABILISI:
L Whenever irradiated fuel is in the reactor vessel and NC Systcm p
wide range level ts less than or equal to 16%.
TEMEDTAL_Ap[1QH:
If any of the above commitments cannot be met during the time that
[
the reactor vessel is in a reduced inventory c'ondition, take immediate corrective actions to bring the plant into compliance
'with the COMMITMENT and contact the Station Manager and/or responsible Group Superintendent for additional guidance.
TESTING T31QMUtEMENTS:
Mone REFERENCF4:
r 1)
Generic Letter 88-17 (Loss of Decry Heat Removal) l 16.5-2 11/91 I
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2)
NUREG 1410 during Mid-Loop Operation at Vogtle)(Lotsa of Vital AC power and 3)=
Catawba Nuclear Station Direc:tive 3.1. 30 (Mid-Loop Operation) 4)
OP/1(2)/A/6150/06 (Drailing the Reactor Coolant System) 5)
Catawba Nuclear Station Technical Specifications 6)
Catawba Nuclear Station Technical Specification Interpretations 7)
Oconee Nuclear Station Select.ed Licensee Commitment 16.5 3 8)
Integrated Scheduling Enagement Procedure 3.1 (Outage Planning and Execution Responsibilities) 9)
Catawba ~ Nuclear Station responses to Generic Letter 88-17 dated January 3, 1989 BASES:
Goncric Letter 88-17 and NUREG 1410 involve with a lons of. Residual IIcat Removal durina NC Syntem reduced concerns associated inventory.
Numerous events have occurred in the industry that
- resulted in a loss of residual het.t removal during reduced inventory operation.. This is of great concern due to the potential for eubstantial core damage occurring-in a relatively short time peric,:1.1
. This-Selected Licensee Commitment depicts those commitments which are extremely important to nuclear safet howeve.r, are.not presently covered by Technica1 Specifications,y, f
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16.5-3 11/91
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9' 16.9 byXTLIARY SYSTEMS FIRE PROTECTION SYSEMS 16.9-6 FIRE DETECTION INSTRUMENTATION COMMITMEHT, As a minimum, thJ ftre detection instrumentation for each fire detection zone shown in Table 16.9-3 shall be OPERABLE.
AEPhlCallEltY:
Whenever equipment protected by the fire detection instrument is required to be OPERABLE.
BEMFD1AL AQE Qti a.
With any, but not more than one-half the total in any fire zone, Function A fire detection instruments shown in Table 16.9-3 irioperable, restore the inoperable instrument (s) to OPERABLE status within 14 days or within 1 aour establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least onr.n por
- hour, unless the instrument (s) is located inside the containment, then inspect that containment zone at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or rnonitor -the containment air temperature at least once per hour at the locations listad in Specification 4.6.1.3.
b.
With nore than one-half of the Function A fire detectior.
instruments in nni fire zone shown in Table 16.9-3 inoperable, or with any Function B
fire detection instruments shown in Table 16.9-3 inoperable, or with any
.two - or rtore adjacent fire detection instruments shown in Tab /n 16'.9-3 inoperable, within 1 hour-establish a fire vc.tch - patrol to inspccP the zone (s) with the inoperable inetrument(s) at loast once por-
- hour, unless the inatrument(s) is located ir. side the containment, then Anspect that containment zone at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.or monitor the containment air temperature at least once por hour at the locations listed in Specification 4.6.1.5.
s TESTING ' REQUIfRilMIE:
a,
'Each of the above required flame detection-instruments shall
.be demonstrated OPERABLE-at least once per 6 months by performance of a TRIP ACTUATING DEVICE OPERATIONAL TEST.
Each of the above required smoke detection instruments which ara accessible-during-plant operation shall be demonstrated
-OPERABLE at least once por 6 months by the performance of a TRIP ACTUATING DEVICE OPERATIONAL TEST. Detectors which are not accessible during plant operation shall be demonstrated 16.9-15 2/92 j
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operabic by -the performance of a
TRIP ACTUATING DEVICE OPERATIONAL TEST during each refueling outage.
All spot. type heat intectors which are accessible dt.r ing plant operation shall be VISUALLY INSPECTED at least once per 6 months.
Ec.ch of the above required heat detection instruments shall be demonstrated OPERABLE as follwws:
1.
For nonrestorable spot-type detectors, at least two detectors out of every hundred, or fraction thereof, chall be removed every 5 years and functionally tested.
For each failure that occurs on the detectors removed, two additional detectors shall be removed and testud; and
- 11. For restorable spot-type heat detectors which are accessible during plant operation, at least one detector on each signal initiating circuit shall be demonstrated OPERABLE at least once por 6 months by performance of a TRIP ACTUATING DEVICE OPERATIONAL TEST.
Difforent detectors shall be selected for each test.
Fire detectors which are not accessible during plant operation shall be demonstrated OPERABLZ by the l
performance of a TRIP ACTUATING DEVICE OPERATIONAL TEST l
during each refueling outage.
b.
The NFPA Standard-72D supervised circuits supervision associated with the detector alarmn of each of the above required fire detection in truments shall bo demonstrated OPERABLE at least once per (
wnths.
REFERENCRE:
1)
Catawba FSAR, Sectior 9.5.1 21 Catawba SER, Section 9.5.1
't )
Catawba SER, Supplement 2, Section 9.5.1 4)
Catawba SER, _ Supplement 3, Section 9.b,1 5)
Catawba Fire Protection Review, as Revised 6)
Catawba-Fire Prclection Commitment Index 16.9-16 2/92 A
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OPERADILITY of the detection instrumentation ensures that both adequate warning capability is available for prompt detectian of fires and that Fire Suppression Systems, that are actuated by fire detectors, will discharge extinguishing agents in a timely marner.
Prompt detection and suppression of tires will reduce the potential for damage to safety-related equipment and is an integral element in the overall facility Fire Protection Program.
Fire detectors that are used to actuhte Fire Suppression Systems represent a more critically important component of a plant's Fire Protection Program-than detectors that are installed solely for early fire warning and notification.
Consequently, the minimu'n number of OPERABLE fire detectors must be greater.
The loss of detection capability for Fire Suppression Systems, actuated by fire detectors, reprasents a significant degradation of fire protection for any area.
As a result, the establishment of a fire watch patrol must be initiated at an earlier stage th22n would be warranted for the loss o t' detectors that provide only car 3y fire warning.
The octablishment of frequent fire patrols in the affccted areau is required to provide detection capability until the inoperable instrumentation is restored to OPERABILITY.
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