ML20072J753
| ML20072J753 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 06/27/1983 |
| From: | Bradley E PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8306300221 | |
| Download: ML20072J753 (7) | |
Text
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PHILADELPHIA ELECTRIC COMPANY 23O1 M ARKET STREET
/
P.O. BOX 8699 PHILADELPHI A. PA.19101 EDW ARD G. S AUER. JR.
eesne A6 covass6 EUGENE J. BR ADLEY A ssOCf ATE GENERAL COVNsE6 DON ALD BLANKEN RUDOLPH A. CHtLLEMI E. C. KI R K H A LL June 27, 1983 ^
T. H. M AH EM CORN ELL PAUL AUENsACH AssesvA=7 ennenA6 counsa6 EDW ARD J. CULLEN. JR.
THOM AS H. MILLER. J R.
IRENE A. Mc MENN A AssssvAnv counsu6 Mr. A.
Schwencer, Chief Licensing Branch No. 2 Division of Licensing U.
S.
Nuclear Regulatory Commission Washington D.C.
20555 s
Subject:
Linerick Generating Station, Units l&2 Loose Parts Monitoring System (LPMS) 5 0 *b 6 'A 50 - h Th Re-f e re n c e :
PECO and NRC Conference Call dated 6/21/83 File:
GOVT l-1 (NRC)
Dear Mr. Schwencer:
As a result of the discussions in the referenced conference call, the attached draft FSAR page changes concerning the Loose Parts Monitoring System will be incorporated into the FSAR, exactly as it appears on the attachments, in the revision scheduled for July, 1983.
As requested by the NRC reviewer, a more detailed system description will be provided to show compliance with Regulatory Guide 1.133.
A schedule will be developed for submittal of this information upon our receipt of the Safety Evaluation Report.
Sincerely, 7
8306300221 830627 Eug ne rad e DR ADOCK 05000352 PDR RJS/gra/54 Copy to:
Sec Attached Service List i
4 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.
(t/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 ecciosure)
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 Gerucky (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 euclosure) e e
em D
LGS FSAR Limerick qualification tests of electric cables, field splices,
}
and connections are discussed in Section 3.11.
(Category 1) 1 REGULATORY GUIDE 1.132 Site Investigations for Foundations of Nuclear Power Plants Rev 1., March 1979 This guide is applicable to Limerick only for new investigations conducted after March 30, 1979.
No new investigations have been conducted since that time.
Site investigations are discussed in Sections 2.4 and 2.5.
(Category 1)
REGULATORY GUIDE 1.133 Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors l
pp9y l9%f/
)
Rev,#,,SeptemberM 977 Limerick is in conformance with Deast-3-of-R6 vision 4 this guide as discussed in Section 4.4.6.1, ah;r: : carperison with-
"- " '-- ^~of-the guide le else renvidad -
(Category 1)
REGULATORY GUIDE 1.134 Medical Certification and Monitoring of Personnel Requiring Operator Licenses Rev 1, March 1979 Limerick will be in conformance with this guide, which endorses / modifies ANSI N546-1976, as discussed in Section 13.1.
2-(Category 1)
REGULATORY GUIDE 1.135 Normal Water Level and Discharge at Nuclear Power Plants Rev 0, November 1977 Rev.
7, 06/S2
.J.8-42 g
. - = - -
=
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throughout core lifetime are discussed in Chapter 14.
A summary of preoperation and initial startup testing is as follows:
a.
Preoperational testing: Tests are performed during the preoperational test program to confirm that construction is complete and that all process and safety equipment is operational.
Baseline data are taken to assist in the evaluation of subsequent tests.
Heat-balance instrumentation and jet pump flow and core temperature instrumentation are calibrated and setpoints verified.
b.
Initial startup: Hot functional tests are conducted with the reactor between 5% and 10% power.
Core performance ic monitored continuously to ensure that the reactor is operating within allowable limits (e.g., peaking factors, LHGR, etc) and is evaluated periodically to verify the expected and actual core performance margins.
4.4.6 INSTRUMENTATION REQUIREMENTS The reactor vessel instrumentation monitors the key reactor vessel operating parameters during planned operations.
This ensures sufficient control of the parameters.
The following reactor vessel sensors are discussed in Sections 7.6 and 7.7:
a.
Reactor vessel temperature b.
Reactor vessel coolant flow rates and differential pressures d.
Reactor vessel internal pressure e.
Neutron monitoring system 4.4.6.1 Loose Parts Monitorino System (LPMS)
J 4'6.1.1 Design Basis s s a.
The LPMS is designed to detect loose parts in the reactor coolant systems.
b.
The LPMS is designed to ceduce the effects of variations in background noise on system capabilities for the detection of -loose parts.
TheLPMSisdesianed/nconformance+41h nrnft 2 tn d5)L c.
y.44 Revision 1 (May i9763 of Regulatory Guide 1.133.
- Dccpti3 Qn Da i <-i nn 1 (May 1981) of the cuide are nuceu ucivw3w__
4.4-25 Rev. 15, 12/82_
l t
DRAFT LeS,,
The Limerick LPMS does not follow Regulator a.
Positio C.1.d in that the system doe not simulta ously record all sensor cha els for future p ayback and analysis.
The stem's
~~
magnetic tape recorder system reco s
event-rel ted parameters simultan usly on four chan 1s only.
Recorder op ation is initiated y the first sensor d ecting a loose part 'mpact' exceeding th preset alert level.
Thi channel, and the others selected by he programmable larm matrix, are automaticall recorded.
Dat thus recorded can then be d agnosed to de ermine mass and location of th loose part This meets the intent of this regulatory position.
b.
The Limerick LPMS do s not f low Regulatory Position C.1.g i that he total system is not tested to the co lete requirements of Regulatory Guides 1.8 and 1.100.
Equipment located in the co tr 1 room is successfully tested to seismic els exceeding operating basis earthquake (
E) criteria at that location.
This eq ment is also protected from damage from th r devices in the same or
)
adjacent cabinet, a the enclosure in which it is located h bee constructed and analyzed to str ctural y survive excitation exceeding the E level.
Equipment external to the contro room has een similarly tested to OBE criter a.
Sensors, eg ipment and sp ial cabling for use inside the rimary contain ent is rated at 10:e V and 50 rem / hour, ga a, and is suitable n
for conti uous operation fro 400F to 6300F at 100 pere t relative humidit.
Equipment located utside the primary c ntainment is constru ted of high quality s id-state electr ic modules.
The envir nmental suitab lity of all component p rts of the syste has been demonstrated by over 20 system year of operation under normal plant oper ting conditions.
c.
The Lim ick LPMS does not follow Regu3atory P
ition C.3.b in that the magnet:.c tape r cording system only records four sensor annels simultaneously, as discuss d in a.
bove.
However, a dedicated microp ocessor-based paper tape recording system do s s
document all channel events with resp'ect to
)
4.4-26
t operating condffions, extracted from other a
ouneer-can then be related i
to these_evenE's.
/
4.4.6.1.2
System Description
The function of this system is to detect and alarm for loose parts in the reactor coolant system.
Loose parts are those metallic objects that can be physically moved by the reactor flow.
A secondary function of the system for the Limerick units is to assist the operators in locating the detected loose parts l
as accurately and quickly as possible.
The devices mounted within each containment are designed to withstand the SSE and are redundant (eight sensors located on opposite sides of each reactor at four elevations).
There are two identical sets of control room equipment, one set dedicated to Unit 1 and one set dedicated to Unit 2.
Isolation is maintained between the monitoring channels up to and including the control room monitors (which contain the alarm circuits).
While these precautions have been taken, the system is not considered safety-related.
l A primary consideration in the design of the LPMS is the power l
s spectrum density (PSD) plot shown in Figure 4.4-19, which l
I illustrates the normal background energy content over a specific band of frequencies of an operating power reactor, as detected by a piezoelectric transducer.
The overall energy content and shape 1
of the plot varies with plant conditions and between different sensor locations.
Salient features demonstrated by the PSD are:
a.
Low-frequency energy is related to the NSSS structure and machinery vibration b.
High-frequency energy is related to flow associated noises c.
Relatively rapid attenuation of the higher-frequency noises occurs because of the filtering effect of the acoustic path through the NSSS components.
The LPMS incorporates tuned bandpass filters to concentrate on the portion of the noise spectrum that has a low background level, generally in the 1 Khz to 10 Khz frequency range.
Because metal-to-metal impacts result in a relatively flat frequency response in the 1-10Khz range and because certain portions of the background noise in that portion of the frequency spectrum are of relatively low level, the signal-to-noise ratio is improved, thereby enhancing detection capability while reducing the occurrence of false alarms.
4.4-27 4
)
120 to 200% of the background energy level is detected.
The detector module also features a low alarm, which is associated with the continuous channel check function.
The low alarm output from the detector modules is routed to the master alarm module only.
The high alarm output of the detector modules is routed to four places:
the master alarm module, the loose parts locator, the matrix switch, and the MARSS (Multiplex Analog Recording and Switching System.).
The master alarm module accepts the high and low alarm outputs of the detectors, illuminates an indicator for the appropriate alarm, and initiates an audio alarm.
The loose parts locator is a digital processor that calculates and displays the time of arrival of each loose part impact at the sensors, thereby assisting the operator in determining the location of the loose part.
The matrix switch improves operational flexibility by allowing all sensor signals, as well as auxiliary inputs of additional data or test signals, to be routed to any available output connection, which includes audio monitors for the sensor signals, a spectrum analyzer or other auxiliary outputs that may be connected to portable diagnostic or analysis equipment.
)
The MARSS provides for the recording of signals as manually selected by the operator during routing system operability checkout.
However, when an alarm (alert) condition is detected, MARSS automatically overrides the manually selected inputs and records the alarm channel and three others selected by the alarm matrix.
The tape recorder is a four-track audio tape recorder that records the loose part signals and an encoded channel identification.
The system is designed to operate continuously without operator supervision, except for routine system testing.
4.4.6.1.3 Safety Evalu3tlon-The LPMS is intended to be used for information purposes only and is not a safety-related system.
The system conforms with Regulatory Guide 1.1337 ;;
gw.
s te t; d ir. 0.0.f."P The plant operators use the LPMS to assist in the detection of anomalous loose parts.
They also use it to assist in determining the location of any anomalous loose parts.
The operators do not rely solely on this system or information provided by this system for the performance of any safety-related action.
Any evaluations or J
actions taken to confirm the presence of a loose part will be handled on a case-by-case basis.
4.4-29 Rev. 15, 12/82
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