ML20076K217
| ML20076K217 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 07/05/1983 |
| From: | Bradley E PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8307080296 | |
| Download: ML20076K217 (8) | |
Text
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PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699 PHILADELPHI A. PA.19101 EDW ARD G. S AU ER, JR.
No esas a6 coumss6 EUGENE J. BR ADLEY assocents osmann6 causess6 DON ALD BLANMEN RUDOLPH A. CHILLEMI E. C. KI R K M A LL T. H. M AMER CO RNELL PAUL AUERB ACH assesvant osmana6 counss6 July 5, 1983 EDW ARD J. CU LLEN, J R.
THOM AS H. MILLER, J R.
OR ENE A. McMEN N A assastanT counss6 Mr.
A.
Schwencer, Chief Docket Nos. 50-352 Licensing Branch No. 2 50-353 Division of Licensing U.
S.
Nuclear Regulatory Comnission Washington, D.C.
20555
Subject:
Limerick Generating Statipn, Units l&2 Request for Information from NRC Containment Systems Branch (CSB)
Re ference :
Meeting, NRC CSB and Philadelphia Electric Company, June 15, 1983 File:
GOVT l-1 (NRC)
Dear Mr. Schwencer:
The enclosed draft FSAR pages contain additional information regarding Isolation of Purge and Vent Valves on High Radiation as requested by CSB at the re ference meeting.
The information contained in these draft FSAR page changes will be incorporated into the FSAR, exactly as it appears in the enclosures, in the revision scheduled for August, 1983.
Sincerely, 8307080296 830705 I
PDR ADOCK 05000352 A
PDR Eue ne Bradley HDH/gra/9I Enclosure Copy to:
See Attached Service List
[
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O cc: Judge Lawrence Brenner (w/o enclosure)
Judge Richard F. Cole (w/o enclosure)
Judge Peter A. Morris (w/o enclosure)
Troy B. Conner, Jr., Esq.
(w/o enclosure)
Ann P. Hodgdon (w/o enclosure)
Mr. Frank R. Romano (w/o enclosure)
Mr. Robert L. Anthony (w/o enclosure)
Mr. Marvin I. Lewis (w/o enclosure)
Judith A. Dorsey, Esq.
(w/o enclosure)
Charles W. Elliott, Esq.
(w/o enclosure)
Jacqueline I. Ruttenberg (w/o enclosure)
Thomas Y. Au, Esq.
(w/o enclosure)
Mr. Thomas Gerusky (w/o enclosure)
Director, Pennsylvania Emergency Management Agency (w/o enclosure)
Mr. Steven P. Hershey (w/o enclosure)
Donald S. Bronstein, Esq.
(w/o enclosure)
Mr. Joseph H. White, III (w/o enclosure)
David Wersan, Esq.
(w/o enclosure)
Robert J. Sugarman, Esq.
(w/o enclosure)
Martha W. Bush, Esq.
(w/o enclosure)
Spence W. Perry, Esq.
(w/o enclosure)
Atomic Safety and Licensing Appeal Board (w/o enclosure)
Atomic Safety and Licensing Board Panel (w/o enclosure)
Docket and Service Section (w/o enclosure)
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LGS FSAR Position (2), Clarification (3)
All systems penetrating containment have been evaluated and identified as either essential or nonessential.
Table 6.2-17 provides the results of this evaluation for each line, and Table 6.2-27 provides the basis for the selection of essential / nonessential systems.
Position (3), Clarification (2)
Systems determined to be nonessential are provided with. diverse, automatic isolation signals, except as described in the response to Position (1).
Manual valves are sealed closed as discussed in Section 6.2.4.3.
Position (4), Clarifications (4), (5)
The control systems for automatic isolation valves are such that resetting the isolation si nal will not result in the automatic reopening of these valves Ganged reopening of containment isolation valves is performed only wnere the operation of multiple valves is required for system operation.
Sample inlet and return valve controls for the drywell radiation monitors and l
combustible gas analyzers are ganged as described in Sections 6.2.4.3.1.3.2.8 and 6.2.4.3.1.3.2.4.
Reactor enclosure cooling water and drywell chilled water. valve controls are ganged as described in Sections 6.2.4.3.1.3.2.10 and 6.2.4.3.1.3.2.11.
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e Position (5), Clarification (6)
The setpoint for the drywell high pressure isolation signal is set at the minimum compatible with normal operation.
Section 7.3.1.1.2.4.6 describes the selection of the drywell high pressure setpoint.
Position (6), Clarification (7)
Containment purge valves comply with Branch Technical Position CSB 6-4 as discussed below.
Two purge isolation valves have closure times greater than 5 seconds: 2"-HV-105 and 2"-HV-111 have closure times of 30 seconds.
An analysis of the radiological consequences of a LOCA that occurs during purging was performed to justify the line size and the valve closure time used in the purge system.
Using the assumptions of BTP CSB 6-4, the resulting doses were a small fraction of the 10CFR100 limits.
For local leak rate tests, the leakage rate of the purge isolation valves, combined with the leakage rate for all other penetrations and valves subject to Type B and C tests will be less than 0.60 La, in accordance with Appendix J to 10CFR50.
Position (7)
The containment purge isolation valves isolate on receipt of an one of the following safety-related isolation signals:
p,
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high drywell pressure goh b.
reactor low water level
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c.
reactor enclosure high radiation g
1 d.
refueling floor high radiation In addition to the safety-related isolation signals listed above, the containment purge Egg vent isolation valves rr:t;; tr_n 2 i--" r i-dirrrter tro' rate on receipt of a no safety-related north stack ef fluent high radiation signalp(see sect 4aw 7,G.I.I AuJ #1.5)
An analysis has been performed to demonstrate that the offsite doses that might result if a LOCA were to occur during purging operations would be less than both 10CFR100 and EPA Protection -
Action Guide limits.
This analysis used the assumptions of NUREG 0800 Section 6.2.4 and Branch Technical Position CSB 6-4 and assumes a pre-existing spike that results in coolant activity levels in excess of Technical Specification limits.
The analysis methodology was in accordance with the letter from T.J. Dente (BWR Owners Group) to D.G. Eisenhut (NRC) " Supplement to BWR Owners Group Evaluation of NUREG 0737 Item II.E.4.2(7)", dated June 14, 1982.
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Outboard suppression pool sample and return isolation valves SV-184, SV-185, SV-186, SV-190, and SV-195 are ganged on HS-187.
6.2.4.3.1.3.2.2 Drywell Equipment and Floor Drain Lines The drywell equipment and floor drain lines are provided with two normally closed air-operated spring-closed valves located outside the primary containment.
The inner valve is located directly on the containment.
Both valves ace automatically closed upon rec <ript of a containment isolation signal.
6.2.4.3.1.3.2.3 Containment Purge and Hydrogen Recombiner Lines The high-volume purge lines for the drywell and suppression chamber are each provided with two isolation valves located outside the primary containment.
The inboard valve in each line is a normally-closed, air-operated butterfly valve located as close as practical to the primary containment penetration.
The outboard valve in each line is a normally-closed, motor-operated butterfly valve.
The hydrogen recombiner lines connect to the high-volume purge lines between the containment penetration and the inboard isolation valve in the latter lines.
Each of the hydrogen recombiner lines is a seismic Category I line and is provided with a normally closed. motor-operated butterfly valve that can be remote manually actuated from the control room.
A description of the type and the arrangement of containment isolation valves used in the low-volume purge exhaust lines is provided in Section 9.4.5.1.2.
The isolation' valves in the containment purge and hydrogen recombiner lines each receive an automatic isolation signal and ensure isolation of these lines.in the event of a break and long-term leakage control.
In addition, the piping is considered an extension of the containment boundary since it must be available for long-term usage following an accident, and as such is designed to the same quality standards as the primary containment.
A nonsafety-related north stack effluent high radiation isolation signal is also provided for the containment purge valvesV h:t _..
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The high-v,olume pu,rge lines are provided with debris screens located at the point where each purge line terminates inside the primary containment.
The debris screens are designated as seismic Category I and are designed to withstand the maximum differential pressure across the screen that could result from a LOCA.
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6 6.2-57 Rev. 2/, 0//83
j LGS-FSAR
)
TABLE 6.2-17 (Cont'd)
(Page 17 of 19)
LFRH With RHR pump running, opens on low flow in associated pipe, closes when flow is above set point M
Low differential pressure between the instrument gas line and the primary containment P*
Low main steam line pressure at inlet to turbine (RUN mode only)
Q*
Low condenser vacuum and turbine stop valve more than 90% open R*
High radioactivity in reactor enclosure or refueling floor ventilation exhaust ducts S*
High radiation in the reactor enclosure T*
Low differential pressure between the outside atmosphere and either the secondary containment or refueling area V*
High reactor pres,sure (shutdown cooling mode only)
Wk North stack effluent high radiation l
Y Standby liquid control system actuated RM*
Remote manual switch from control room (all power-operated isolation valves are capable bf being operated remote-manually from the control room) i
- These are the isolation functions of the primary con-tainment and reactor vessel isolation control system; other functions are given for information only.
(6)
The standard minimum closing rate for automatic isolation gate valves is based on a nominal line. size of 12 inches.
Using the standard closing rate, a 12-inch line is isolated in 60 seconds.
Conversion to closing time can be made on this basis using the actual size of the line 'in which the gate valve is installed.
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LGS FSAR ggsQJ The stack radiation monitoring system, including the isokinetic sampling system and the wide-range accident monitoring subsystem, is designed to carry out the following functions:
a.
To provide continuous isokinetic and representative samples of the stack flow in compliance with the requirements of General Design Criterion 64 of 10CFR50, Appendix A, Regulatory Guide 1.21, and ANSI 13.1-1971.
b.
To continuously record releases of radioactive-particulates, iodines and noble gases to the environs so that the total quantity of radioactive material released can be evaluated, c.
To alarm, in event that specified rates of release of l
radioactive material are exceeded.
d.
To provide continuous real-time indications of
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radioactive releases during the accident and post-accident modes of operation.
e.
Provide an isolation signal to the containment purge valves ;;r:_R: th r ? inch h in the event of l
high radiation in the north stack effluent.
The north stack exhausts from the following systems:
I a.
Unit I turbine enclosure exhaust b.
Unit 1 turbine enclosure equipment compartment exhaust (including mechanical vacuum pump exhaust) c.
Unit 2 turbine enclosure exhaust d.
Unit 2 turbine enclosure equipment compartment exhaust (including mechanical vacuum pump exhaust) l l
e.
Radwaste enclosure equipment compartment exhaust f.
Radwaste enclosure fume hood exhaust g.
Radwaste service and control area exhaust 3
8 11.5-11 Rev. 2[,O//83 j
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