ML20236B076
| ML20236B076 | |
| Person / Time | |
|---|---|
| Issue date: | 03/06/1989 |
| From: | Butcher E Office of Nuclear Reactor Regulation |
| To: | Rossi C Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8903200326 | |
| Download: ML20236B076 (11) | |
Text
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VAR 6 1989 MEMORANDUM FOR:
Charles E. Rossi, Director
' Division of Operational Events Assessment, NRR-p FROM:
Edward J. Butcher, Chief Technical Specifications Branch:
Division of Operational Events Assessment, NRR I
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SUBJECT:
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ft1NUTES OF MEETING WITH NUMARC TASK GROUP WHICH IS WRITING NEW STS FOR PLANT SYSTEMS f
On Friday, December 2, 1988, the staff met with the NUMARC task group which is l
writing the'new Standard Technical Specifications (STS) plant system sections to l
hear their early estimate of anticipated technical changes. The staff was also interested in discerning any technical change that might require a review effort outside the normal STS review process.
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.The task group provided a handout (attached) of several marked up Comt'ustion Engineering Standard Technical Specifications pages and one marked up
.f Comanche Peak-Unit 1 technical specifications page. Some of the marked up pages indicate technical changes to be proposed with the new STS. 'Other marked up pages, however, relate to the task group's ongoing efforts to resolve some of the their own questions.
The following coments relate to the marked up technical specifications pages:
1 LCO 3.7.1.1:
TURBINE CYCLE SAFETY VALVES The task group commented that no accident analysis nor the ASME Code requires more than one code safety valve per steam generator to be operable in MODE 3.
LCO 3.7.3:
COMP 0NENT COOLING WATER SYSTEM The task group would like to add an action statement which allows 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to repair one train if two trains are inoperable.
The task group commented that with tuo trains of component cooling water inoperable, a plant is required to shutdown; but it it unable to shutdown without cooling. The task group comented that the same situation exists for the service water system.
LCO 3.7.7:
CONTROL ROOM EllERGENCY AIR CLEANUP SYSTEM For MODES 5 and 6, ACTION a., the task group is questioning the bases for placing the operable system in the recirculation mode.
'f The task group will explore the technical bases for the specification and 1,h offer a clarified text.
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"ECCS PUMP ROOM EXHAUST AIR CLEANUP SYSTEM e m A..
- The-task group would like to add an. action statement.which allows 24-hours to repair'one. train if two trains are inoperable.. They would-like to' add a similar action statement on other similar systems.
d The staff commented that there did not seem to be a clear basis for adding such an additional action-statement.
B.
For Surveillan'ce' Requirement 4.7.8.b.(2), the' task group ' questioned' '
how much painting was incant.by the words, "following; painting."
The task group will explore several technica1' options to clarify the term.
C.
For.. Surveillance Requirement 4.7.8.c., the task group would like to increase the Surveillance Intervals (SI) from 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br />.to 1440 hours0.0167 days <br />0.4 hours <br />0.00238 weeks <br />5.4792e-4 months <br /> because'some plants have raported that testing after 720.' hours reveals no problems.
The staff commented that' plants with plant specific supporting data
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would be allowed'to increase their SI to 1440 hours0.0167 days <br />0.4 hours <br />0.00238 weeks <br />5.4792e-4 months <br />.
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D.
The ta'sk group would like to relocate Surveillance Requirement 4.7.8.d.
I outside.of. technical specifications.
.The. task' group commented that the filter cooling bypass valves are not -
assumed in any-accident analyses. and,that the valves are not needed-1
.until-after an accident.
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FUEL STORAGE: POOL AIR CLEANUPESYSTEM (Comanche Peak)
The task grou'p proposed a. clarification;to ACTION "a."'
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'The task group commented that while.other. proposed' technical changes could develop, the above are the most sig'ific:nt ones known at theitime'of the meeting.
n With respect to situations 6:here proposed technical changesaarefof thb nature'
.of. relocating technical specification requirements outside of. technical specifications, the staff position is presented in the "spl.it report" dated May 9, 1988. The staff does not anticipate revisiting these issues.' 0therwise,
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the staff did not identify any technical change that would require a review H
effortoutsidethenormt.1STSreviewl. process.'
Original Signed By:
Edw$rdd. Butcher, Chief Edwa'rd J. Butcher
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Technical Specifications Branch Division of Operational Events Assessment, NRR j
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Enclosures:
As stated DISTRIBUTION:
Please see attached (MEM0 MINUTES 12/2 MARK)G)Cl J[
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MAR 6 1989 I
MEETING ATTENDEES l
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i Name Affiliation-J Stewart Webster
. Combustion Engineering Art Bivens
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Cindy Blay Toledo Edison /B&WOG, Dan Green.
Florida Power Corporation /B&WOG i
Jacquie Hinds PG&E
~ Richard Auerswald
. Westinghouse Rob Woolley GA-ISC SPEC-SERVICES' j
i Mark Reinhart NRC/NRR/0TSB Kulin Desai NRC/NRR/0TSB
. Chang-Yang Li NRC/NRR/SPLB l
Charles Nichols NRC/NRR/SPLB 1
William Le Fave-NRC/NRR/SPLB 1
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3/4.7 PLANT SYSTEMS
'f 3/4.7.1 TUR8INE CYCLE
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SAFETY VALVES
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LIMITING CONDITION FOR OPERATION i
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m 3.7.1.1 All sain staan line code safety valves shall be OPERA 8LI with lift settings as specified in Table 3.7.
APPLICABILITY: MODES 1, 2 and 3.
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ACTION:
i a.
With both reactor coolant loops and associated steam generators..
in operation and with'one or sort main steaa line code safety valves. inoperable, eneration in MODES 1, 2 and 3 may proceed -
provided, that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either the inoperable valve is restored to'0PERA8LE status or the Power Level-High trip setpoint '
is reduced per Table 3.7-2; otherwise, be in at least HOT STANOBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
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b.
With one reactor coolant loop and associated steam generator'in operation and with one or mora main steam line code safety valves associated with the operating steam generator inoperable, operation in MODES 1, 2 and 3 may proceed provided:
1.
That at least (2) sain steam line code safety valves on the nonoperating steam generator are OPERABLE, and 2.
That within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either the inoperable valve is restored to OPERABLE status or the Power Level-High trip setpoint is reduced per Table 3.7-3; otherwise, be in at least HOT l
STANOBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
c.
The provisions of Specification 3.0.4 are not applicable.
, SURVEILLANCE REQUIREMENTS 4.7.1.1 No additional Surveillance Requirements other than those required by Specification 4.0.5.
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CE-STS 3/4 7-1 OCT 16 1373
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[c PLANT SYSTEMS 3/4.7.3 COMPONENT COOLING WATER SYSTEM 1
LIMITING CONDITION FOR OPERATION
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3.7.3-At least two independent component cooling water loops shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3 and 4.
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With only one component cooling water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANOBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
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SURVEILLANCE REQUIREMENTS 4.7.3 At least two component cooling water loops shall be demonstrated C
OPERABLE:
a.
~ At least once per 31 days by verifying that nach valva (manual, power operated or automatic) servicing safety related equipment
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that is not locked, sealed, or otherwise secured in position, is I
in its correct position, j
b.
At least once per 18 months during shutdown,~ by verifying that
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each automatic valve servicing safety related equipment actuates
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to its correct position on a test signal.
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PLANT SYSTEMJ 3/4.7.7 CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM LIMITING CONDITION FOR OPERATION 3.7.7 Two independent control room emergency air cleanup systans shall be OPERABLE.*
APPLICABILITY: ALL MODES ACTION:
MODES 1, 2, 3 and 4:
h fC, g With one control room emergency air cleanup system inoperable, restore the
- O ppb, inoperable system to OPERABLE status within 7 days or be in at least HOT p
STANOBY within the next.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following
-th 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
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With one control room emergency air cleanup system bgrable, restore the inoperable system to CPERABLE status within 7 days or initiate and maintain operation of the remaining OPERABLE control J()p_
room emergency air cleanup system in the recirculation mode.
b.
With both control room emergency air cleanup systems inoperable, or with the OPERA 8LE control room emergency air cleanup system, required to be in the recirculation mode by ACTION (a), not capable of being C,
powered by an OPERABLE emergency power source, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.
SURVEILLANCE' REQUIREMENTS 4.7.7 Each control room emergency air cleanup system shall be demonstrated OPERABLE:
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the control room air O '
a.
temperature is less than or equal to (120)"F.
b.
At least once per 31 days on a STAGGERED TEST BASIS by initating, from the control room, flow through the HEPA filters and charcoal
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adsorbers and verifying that the system operates for at least
.15 minutes (10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with the heaters on).
c.
At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system by:
1.
Verifying that with the system operating at a flow rate of cfm + 10% and exhausting through the HEPA filters and charcoal adsorcers, the total bypass flow of the system to the facility vent, including leakage through the system diverting valves, is less than or equal to 1% when the system is tested by admitting cold 00P at the system intake. (For systems with diverting valves.)
CE-STS 3/4 7-16
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3/4 7.8 ECCS PUMP ROOM EXHAUST AIR CLEANUP SYSTEM 4
LIMITING CONDITION FOR OfERATION 3.7.8 Two inderintent ECCS pump room exhaust air cleanup systems sih11 he j
APPLICABILITY: MODES 1, 2,_3 and 4.
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ACTION:
j With one ECCS pump room exhaust air cleanup system ' inoperable, restore the inoperable system to OPERABLE status within 7 days or be in at least HOT STANOBY wittiin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following-30
- hours.
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y SURVEILLANCE RE0VIREMENTS i
Each ECCS pump room exha'st. air cleanup system shall be demonstrated 4.7.8 u
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OPERABLE:
'J a.
At least once per 31 days on a STAGGERED TEST BASIS by initiating,
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t from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 15 minutes (10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with the heaters on).
l b.
At least once per 18 months or (1) after any structural maintanarg
_ en the WDa filter or charcoal adsorter housinos for (2) following painting, fire or chemical release in any ventilation zone communi-L i
cating with the system by:
f 1.
Verifying that with the system operating at a flow rate of cfm + 10% and exhausting through tne HEPA filters and charcoal
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adsorbers, the total bypass flow of the system to the facility vent, including leakage through the system diverting valves, is less than or equal to 1% when the system is tested by admitting cold 00P at the system intake. (For systems with diverting valves.)
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,t PLANTSYSTEMS-l SURVEILLANCE REQUIREMENTS (Continued)
"~'; I 'l' 2. Verifying that the cleanup system satisfies the in place
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q tut'.cg acceptanca critaria,and uses the test procedures of-1 Regulatory Pesitions C.S.a. C.S.c and C.S.d of Regulatory Guide 1.52, Revision 2, March 1978, t.nd the system flow rate is~
cfm,;10%.
3.
Verifying within 31 days after removal that a laboratory
, analysis of a representative carbon sample obtained in j
accordance with Regulatory Position C.6.b of Regulatory j
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Guide 1.52, Revision 2,' March 1978, meets the laboratory j
-.-J testing critaria of Regulatory Position C.6.a of Regulatory j
Guide 1.52, Revision 2, March 1978.
1 4.
Verifying a rystem flow rata of cfm 2 10% during i
l l1 { Q system operation when tasted in accorcance with ANSI H510-1975.
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Aff.ar. e ry 720.h s of charcoal adsorber operation by verifying v:ithin 3 tar removal that a laboratory analysis of a
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representative carbon sample obtained in accordance with Regulatory j
. Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, j
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meets the laboratory tasting critaria of Regulatory Position j
C.G.a' of Regulatory Guide 1.52, Ravision 2 March 1978.
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d.
At least once per 18 months by:
1.
. Verifying that the pressure drop acrosJ the combined HEPA filters rnd charcoal adsorber banks is less than (6) inches
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Water Gauge while operating the system at a flow rate of f
cfm 2 10%.
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2.
Verifying that the syster starts on a Safety Injection Actuation Test Signal.
3,~~~~ Verifying that the filter cooling bypass valves can bN f
manually opened.
4.
(Verifying that the heaters dissipate 2
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when wated in accordance with ANSI N5T6 Tf73.)
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s REFUELING OPERATIONS 3/4.9.12 FUEL JTORAGE POOL AIR CLEANUP SYSTEM I
IMITING CONDITION FOR OPERATION 1
3.9.12 Two independent Fuel Storage Pool Air Cleanup ' Systems shall be OPEP,ABLE.
APPLICABILITY-Whenever irradiated fuel is in the storage pool.
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ACTION:
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j With one Fuel Storage Pool Air Cleanup System inoperable, fuel a.
movement within the storage pool or crane operation with loads over the storaga pool may proceed provided the OPERABLE Fuel Storage Pool L
t cp, Air Cleanup System is capable of being powered from an OPERABLE g
emergency power source and,is in operation and discharging through I
least one train of htra ritter) ano cnarcoal adsorbers.
at b.
With no Fuel Storage Pool Air Cleanup System OPERABLE, suspend all operations involving movement of fuel within the storage pool or cranc operation with loads over the storage pool until at least one J
Fuel $torage Pool Air Cleanup System is restored to OPERABLE status.
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The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
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SURVEJLLX]iCEREQUIRENENTS
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4.9.12 The above required Fuel Storage Pool Air Cleanup Systems shall be
'f demonstrated OPERABLE:
At least once per 31 days on a STAGGERED TEST BASIS by initiating, j
a.
f from the control room, flow thrcugh the HEPA filters and charcoal i
adsorbers and verifying that the systeln operates for at least f
10 continuous hours with the heaters operating; l
b.-
At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, firo, or chemical release in any ventilation zone J
i cosusunicating with the system by:
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