ML20072K360
| ML20072K360 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 07/01/1983 |
| From: | Bradley E PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8307060245 | |
| Download: ML20072K360 (11) | |
Text
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PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. DOX 8699 PHILADELPHI A, PA.19101 CDW A RD O. B AUER. J R.
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- ' ::":::'a'".'s.....
CUGENE J. BR ADLEY assoceave eensmaL counest DONALDBLANKEN RUDOLPH A. CHILLEMI hy 1, MM E.C."'"""^"
T. H. M AH E R CORN ELL PAUL AUERBACH asseavant esnansk counsek EDW A RD J. CULLE N, J R.
THOM AS H. MILLER, J R.
IR EN E A. Mc K EN N A assesvant counes6 Mr. A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing U. S. Nuclear Regulatory Conmission Washington, DC 20555
SUBJECT:
Lirrerick Generating Station, Units 1 & 2 Information for Containnent Systems Branch (CSB)
REFE11ENCE:
1.
PECo. letter E. J. Bradley to A. Schwencer dated May 10, 1983 2.
PECo. letter fran E. J. Bradley to A. Schwencer dated June 23, 1983
Dear Mr. Schwencer:
Attached are draft revised Sections 6.2.4 and 7.3 and Table 6.2-17 of the FSAR reflecting our position on CSB draft SER item 15 with regards to automatic isolation of the DGV and RE01 containment isolation valves. This revises sone of the pages transmitted in Reference 1 for itan 15.
'Ihe attached Table 6.2-17 supercedes the draft revised table transmitted in reference 2.
This should close out CSB dr SER item 15.
kii,'
830/060245 830701 PDR ADOCK 05000352 E
. The infonration contained on these draft FSAR page changes will be incorporated into the FSAR, exactly as it appears on the attachnents, in the revision scheduled for July, 1983.
Sincerely, i
/
l Euger J.
radley SM/mjb 6/21/83-1 Copy to: See attached service list.
I 1
l
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 1. 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) 4 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) 4 I
Docket and Service Section (w/o enclosure) a
[
ggg77 ans LGS FSAR 6.2.4.3.1.3.2.8 Drywell Radiation Sampling Lines The sampling system lines that penetrate the containment and connect to the drywell and suppression chamber air volume are equipped with two normally open soler.oid-operated isolation valves in series, located outside and as close to the containment as possible.
These valves ensure isolation of these lines if there should be a break; they also provide long-term leakage control.
In addition, the piping is considered an extension of the containment boundary and, as such, is designed to the same quality standards as the primary containment.
The drywell radiation sampling isolation valves have ganged controls for reopening.
Inboard sample and return isolation valves SV-190A and SV-19CC are ganged on HS-190A.
Outboard sample and return isolation valves SV-190B and SV-190D are ganged on HS-190B.
6.2.4.3.1.3.2.9 Primary Containment Instrument Gas The influent lines are provided with a normally-open power-operated globe valve outside the containment and a check valve inside the containment.
Motor-operated valves are used on the influent lines that contain the ADS gas supply.
These are essential lines that provide a long-term backup to the ADS accumulators inside containment.
The valves on these essential lines are remote manually operated and automatically isolate only when flow out of containment through these lines would be possible (i.e.,
low differential pressure between the containment and the instrument gas line).
The remaining influent lines are non-essential. lines that use air-operated valves that are automatically closed on receipt of a containment isolation signal.
The effluent lines are provided with normally-open air-operated globe valves inside and outside the containment that close automatically on receipt of a containment isolation signal.
6.2.4.3.1.3.2.10 Reactor Enclosure Cooling Water l
Each influent and effluent line is provided with two gate valves located outside containment.
The inboard valves are motor-operated.
The outboard valves on the emergency service water intertie lines are locked closed.
The outboard valves on the RECW lines (HV-108 and HV-111) are motor-operated and their controls are ganged on HS-108.
Each of the motor-operated valves can be remote ranually closed from the control room..aemete ss url ::tuttier it r :!;;et : L;;:::: cyct:
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6.2.4.3.1.3.2.11 Drywell Chilled Water Each influent and effluent line is provided with two motor-operated gate valves located outside containment.
The controls for these valves are ganged as follows:
a.
Loop A inboard influent and effluent isolation valves l
HV-128 and HV-129 are ganged on HS-128.
b.
Loop B inboard influent and effluent isolation valves HV-122 and HV-123 are ganged on HS-122.
c.
Loop A outboard influent and effluent isolation valves I
HV-120A, 121A, 124A and 125A are ganged on HSS-121A.
d.
Loop B outboard influent and effluent isolation valves r
HV-120B, 121B, 124B and 125B are ganged on HSS-121B.
The inboard valves are provided with automatic isolation signals as indicated in Table 6.2-17.
The outboard isolation valves are aligned to either the drywell chilled water system or the reactor enclosure cooling water system.
By the end of the first refueling outage, the controls for the outboard valves will be modified top" $ )phr k A N 5 b AWh & c' 5 & rk'f![ k k,' --- ~
Nr 6.2.4.3.1.3.3 Conclusion on Criterion 56 In order to ensure protection against the consequences of accidents involving release of significant amounts of radioactive materials, pipes that penetrate the containment have been demonstrated to provide isolation capabilities on a case-by-case basis in accordance with Criterion 56.
In addition to meeting isolation requirements, the pressure retaining components of these systems are designed to the same quality standards equivalent to those used for the primary containment.
l l
6.2.4.3.1.4 Evaluation Against Criterion 57 Criterion 57 describes criteria for closed system isolation valves.
Influent and effluent-lines of this group are isolated by automatic or remote manual isolation valves located as close as possible to the containment boundary.
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LGS-FSAR l TABLEki,2-17(Cont'd) (Page 19 of 19) ~ # (11) Thecontrolroddrive(lRD)insertandwithdraw 1 g lines can be isolated by solenoid valves outside d containment. Air operated scram inlet and outlet ( valves are also provided. Leakage may occur through the scram outlet valves. A low leakage flowrate will be treated by the clean radweste system. Excessive l 1eakage will result in either automatic scram or j operator initiated scram. When scram is complete, the scrsn discharge volume system is automatir. ally isolated by the redundant vent and drain valves. (12) Only non-essential systems require diverse signals for automatic isolation. Therefore, this column is not applicable, (NA), for e 1 systems. These valves are norma 11yTelosed and will onlylr (13) be opene6 for flushy' ofthe erxdessefe o/Redmr7 spher /adej darry G, t, a renf,,,,,,,,,,,f jop sg). p (14) Diverse isolation signals are not sensed as discussed in Section 6.2.4.3.1. (15) These valves are normally closed, will be open only during reactor shutdown, are interlocked to open only on low reactor pressure, and connect to a closed system outside containment. Therefore, closure times icss than 60 seconds are not required. l DA DIVt!;te *Mb^wekb /so/gfen lyd to k a/kf s Ay neem 1xe sdnic</y,ed e. y l l T1001550-01V Rev. 21, 06/83
DRAFT LGS FSAR RCIC and HPCI systems are placed in operation. The setting selected is low enough to allow the removal of heat from the reactor for a predetermined time following the scram and high l enough to complete isolation in time for the operation of ECCS if there is a large break in the RCPB. The pipelines that are isolated when the reactor vessel water level falls to this second setting are listed below, a. Reactor water cleanup b. Containment atmospheric control including H,0, sample lines c. Traversing incore probe d. Main steam sample e. HPCI pump flush f. RHR vacuum relief g. Drywell sump drains h. Suppression pool cleanup i. Drywell radiation sample j. Recirculation loop sample l 4 drywellchilledwated The third (and lowest) of the reactor vessel low water level isolation settings (level 1) is the water level setting used to initiate RHR, core spray, and automatic depressurization system, and to start the diesel generators. The pipelines that are isolated when the reactor vessel water level falls to this third setting are the main steam, main steam line drain, containment instrument gas, RHR heat exchanger vent valves, suppression pool and core spray pump test and flush. Reactor vessel low water level signals are initiated from eight differential pressure sensors, four sensors for the level 1 and level 2 trip and four sensors for the level 3 trip, as shown in Figure 5.1-4. They sense the difference between the pressure caused by a constant reference leg of water and the pressure caused by the actual water level in the vessel. Four pairs of instrument sensing lines, attached to taps above and below the water level on the reactor vessel, are required for the differential pressure measurement and terminate outside the drywell and inside the reactor enclosure. They are physically Rev. 21, 06/83 7.3-34 I t ...my - - - - --- - =
ge. $is,wn w fa bkYONC#;Ab RHR shutdown cooling injection outboard throttling motor-operated valves is initiated by logic trip relay B. Tripping of the logic trip relay requires tripping of the two-out-of-two logic for low reactor vessel water level signal or the one-out-of-two logic for reactor low essure signals. nlopr A k Closure of the&drywell chilled water isolation valve is initiated by any one of the followingteonditions a one-out-of-one logies reactor level below level 6X trip; high drywell pressures.high radiation in the reactor enclosure ventilation exhaust duct; high radiation in the refueling floor ventilation exhaust duct. Closure of the inboar.d and outboard reactor water sample motor-operated valves and reactor steam sample air-operated valves is initiated by low reactor vessel water level and high steam line radiation signals, utilizing two-out-of-two logic. Logic trip relay A closes the inboard valves and logic trip relay B closes the outboard valves. Retraction of the TIP drives is initiated by low reactor vessel water level 2 and high drywell pressure in a two-out-of-two logic. Logic trip relay A initiates retraction of the TIP system drives. Closure of the primary containment purge valves is initiated by any one of the following conditions in a two-out-of-two logic: reactor level below level 2 trip; high drywel) pressure; high radiation in the reactor enclosure ventilation exhaust duct; high radiation in the refueling floor ventilation exhaust duct. Closure of the inboard and outboard RWCU isolation motor-operated valves is initiated by low reactor vessel water level utilizing two-out-of-two logic or by high area temperature and high differential RWCU flow utilizing one-out-of-one logic. Logic trip relay A closes the inboard valve and logic trip relay B closes the outboard valves. Closure of the inboard containment instrument gas system (CIGS) suction valve is initiated by any one of the following conditions in a two-out-of-two logic: Reactor level below level 1 trip; high drywell pressure; high radiation in the reactor enclosure ventilation exhaust duct; or high radiation in the refueling floor ventilation exhaust duct. Closure of the primary containment atmosphere sample isolation valves and the post-LOCA hydrogen recombiner isolation valves is initiated by any one of the following conditions in a one-out-of-one logic: Reactor level below level 2 trip; high drywell pressure; high radiation in the reactor enclosure ventilation exhaust duct; high radiation in the refueling floor ventilation l exhaust duct. Closure of outboard CIGS isolation valves not on ADS gas supply lines is initiated by any one of the following conditions in a two-out-of-two logic: Reactor level below level 1 trip; high drywell pressure; high radiation in-the reactor enclosure ventilation exhaust duct. 7.3-45 Rev. 21, 06/83 -.}}