ML17160A486
| ML17160A486 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 12/15/1993 |
| From: | Weiss S Office of Nuclear Reactor Regulation |
| To: | FRANKLIN COUNTY, MA |
| References | |
| NUDOCS 9312230146 | |
| Download: ML17160A486 (7) | |
Text
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Docket Nos.
50-387 and 50-388 HEHORANDUH FOR:
THRU:
FROH:
SUBJECT:
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 16, 1993
" Docket File Larry Nicholson, Acting Director~ -~
Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation Richard J. Clark, Senior Project Hanager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation SUS(UEHANNA STEAH ELECTRIC STATION, UNITS 1
AND 2, INTERPRETATION OF TS SECTION 3.3.2 The situation at Susquehanna is as follows:
1.
Susquehanna Unit 1 has replaced all 20 jet pump beams and started to reload the core at 8:45 p.m.
on December 14, 1993 2001.". g,,
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2.
Unit 2 shut down Saturday morning (12/ll/93) because of a leak in the Reactor Building Closed Cooling Water System (RBCCW) inside containment.
The unit is in cold shutdown.
3.
Because Unit 2 is shut down,Bulletin 93-03 requires that they install the vessel level instrument reference leg continuous keep-fill modification.
The licensee has been running -the piping and instrumentation outside containment for several months.
The licensee started tying into one reference leg at a time on December 15, 1993.
For up'o 4 days, there will be only one rather than two operable water level systems on,Unit 2.
4.
TS Table 3.3.2-1 on Isolation Actuation Instrumentation requires that there be two (2) operable trip systems for reactor vessel water level-low low, level 2.
A footnote, states that this requirement also applies when handl'ing.irradiated fuel'n the secondary containment and during core, alterations and operations with a potential for draining the reactor vessel.
The required action is to establish secondary containment integrity with the standby gas treatment system operating within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
e 5.
At Susquehanna, secondary containment encompasses, both the common Unit 1 and Unit 2 refuel floor.
6.
Operating the standby gas treatment system while personnel are on the refuel floor exposes them to high temperatures and humidity.
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7.
During the 4 days that there will only be one operable water level trip system in Unit 2, the licensee will not be doing any work that would create the potential for draining the reactor vessel.
It is PP&L's position that with Unit 2 in cold shutdown and no core alterations in process, the requirement to have two operable water level trip systems for Unit 2 does not apply.
NRR (Projects, Technical Specifications Branch and Reactor Systems Branch) agree with PP&L's position.
Region I also agrees with PP&L's position.
Enclosures:
1.
TS Pages 3/4 3-11 and 3/4 3-16 2.
PP&L Letter dated 12/14/93, PLA-4062
'c C ark, Senior Project Manager roject Dir ctorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
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TABLE 3. 3.2-l I SOl AllON ACTUATlON TNSTRUHENTATlON TRIP FUNCI ION ISO'LTON SlCNAl(S)(a HININjH APPLTCABLE OPERABLE CHANNELS OPERAT lONAL
~r ACTION 2.
PRIHARY CONlAINIENT lSOLAT lON a.
Reactor Vessel Mater Level 1)
Low, Level 3
2)
Lm Low, Level 2 3)
Lm Low Lut, Level 1
b.
Drywell Pressure
" High c.
Hanual initiation d.
SGTS Exhaust Radiation-High e.
Hain Steam Line Radiation-High SECONDARY CONTAINHENT 1 SOLATlON Y,Z NA 1, 2, 3
1, 2, 3
1, 2, 3
1, 2, 3
1, 2, 3
20 20 20 20 21 1, 2, 3
20
]
2 3
1AAA 5AAA 20 a.
b.
C.
Reactor Vessel Mater Level-Lmr Lme, Le'vel 2 Drywell Pressure
- High Refuel Floor High Exhaust Duct Radiation " High 1, 2, 3 and
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1, 2, 3
25 25 25 EA Pg 0
d.
Railroad Access Shaft Exhaust Duct Radiation - High e.
Refuel Floor Mall Exhaust Duct Radiation - High f.
Hanual initiation 1, 2, 3 and
~
25 25 21
ACTION 2O ACTION 21 ACTION 22 ACTION 23 ACTION 24-
. ACTION 25 ACTION 26 TABLE 3. 3. 2-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION ACTION STATEMENTS Be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Be in at least STARTUP with the associated isolation valves closed within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Be in at least STARTUP within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
Close the affected system isolation valves within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and declare the affected system inoperable.
Restore the manual initiation function to OPERABLE status within & hours or close the affected system isolation valves within the next hour and declare the affected system inoperable or be in at least HOT SHUTDOWN within 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 SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Establish SECONDARY CONTAINMENT INTEGRITY with the standby
- gas, treatment system operating within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
Lock the affected system isolation valves closed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and declare the affected system inoperable.
TABLES NOTATIONS
- ,When handling irradiated fuel in the secondary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.
Actuates dampers shown in Table 3.6.5.2-1.
When VENTING or PURGING the drywell per Specification 3.11.2.8.
(a)
See Specification 3.6.3, Table 3.6.3-1 for valves which are actuated by.
these isolation signals.
(b)
A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillance without placing the channel or trip system in the tripped condition provided at least one other OPERABLE channel in the same trip system is monitoring that parameter.
In addition, for the HPCI system and RCIC systei isolation, provided that the redundant isolation valve, inboard or outboard, as applicable, in each line is OPERABLE and all required actuation instrumentation for that valve is OPERABLE, one channel may be placed in an inoperable status for up o 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for required surveillance without placing the channel or trip system in the tripped condition.
SUSQUEHANNA - UNIT 2 3/4 3-16