ML20153G576
| ML20153G576 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 09/25/1998 |
| From: | Cruse C BALTIMORE GAS & ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9809300123 | |
| Download: ML20153G576 (6) | |
Text
_ _ _ _ _ _ _ _ _ _ - _ _
CHARLES II. CRUSE Baltimore Gas and Electric Company Vice President Calvert Cliffs Nuclear Power Plant Nuclear Energy 1650 Calvert Cliffs Parkway Lusby, Maryland 20657 410 495-4455 September 25,1998 U. S. Nuclear Regulatory Commission Washington, DC 20555 A'ITENTION:
Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50-317 & 50-318 Response to Requet for Additional Information for the Review of the Calvert Cliffs Nuclear Povs : "lant, Units 1 & 2, Integrated Plant Assessment Report for hRadiation Mor ternig System
REFERENCES:
(a)
Letter from Mr. C. H. Cruse (BGE) to NRC Document Control Desk, dated May 23,1997," Request for Review and Approval of System and Commodity Reports for License Renewal" j/
(b)
Letter from Mr. D. L. Solorio (NRC) to Mr. C. H. Cruse (BGE), dated
/
August 6,1998," Request for Additional Information for the Review of the Calvert Cliffs Nuclear Power Plant, Units 1 & 2, Integrated Plant hg Assessment Report for Radiation Monitoring System" Reference (a) forwarded four Baltimore Gas and Electric Company system and commodity reports for license renewal. Reference (b) forwarded questions from 'NRC staff on one of those four reports, the Integrated Plant Assessment Report for the Radiation Monitoring System. Attachment (!) provides our responses to the questions contained in Reference (b).
9809300123 980925 PDR ADOCK 05000317 P
Document Control Desk September 25,1998 Page 2 i
Should you have further questions regarding this matter, we will be pleased to discuss them with you.
Very truly yours
/
STATE OF MARYLAND
- TO WIT:
COUNTY OF CALVERT I, Charles H. Cruse, being duly sworn, state that I am Vice President, Nuclear Energy Division, Baltimore Gas and Electric Company (BGE), and that I am duly authorized to execute and file this response on behalf of BGE. To the best of my knowledge and belief, the statements contained in this document are true and correct. To the extent that these statements are not based on my personal knowledge, they are based upon information provided by other BGE employees and/or consultants. Such information has been reviewed in accordance with company practice and I believe it to be reliable.
i l
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,*w r
Subscribed and sworn before me, a Notary Public in and for the State of Maryland and County of Onluerf
,this 27 day of Swkmber,1998.
WITNESS my Hand and Notarial Seal:
- dII.
Notary Public (ddOR My Commission Expires:
j
/ Date CHC/KRE/ dim
Attachment:
(1) Response to Request for Additional Information; Integrated Plant Assessment Report for the Radiation Monitoring System cc:
R. S. Fleishman, Esquire C. I. Grimes, NRC J. E. Silberg, Esquire D. L. Solorio, NRC S. S. Bajwa, NRC Resident Inspector, NRC A. W. Dromerick, NRC R.1. McLean, DNR H. J. Miller, NRC J. H. Walter, PSC
4 ATTACHMENT (1) 1 i
i f
s RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION; INTEGRATED PLANT ASSESSMENT REPORT FOR TIIE RADIATION MONITORING SYSTEM Baltimore Gas and Electric Company Calvert Cliffs Nuclear Power Plant September 25,1998
ATTACHMENT (1)
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION; INTEGRATED PLANT ASSESSMENT REPORT FOR Tile RADIATION MONITORING SYSTEM NRC Ouestion No.1 In Section 5.14.1.1, System Level Scoping, the process Radiation Monitoring System (RMS) includes the following radiation monitors: plant main vent, waste gas discharge, liquid waste processing discharge, condenser air removal discharge, steam generator blowdown tank discharge, steam generator blowdown recovery, and atmosphere (other than the control room ventilation). In Section 5.14.1.2, Component Level Scoping, all of the above radiation monitors are excluded for the consideration of component level scoping. Provide thejustification for eliminating each of the above radiation monitors from the scope of the license renewal.
BGE Response The radiation monitors that monitor the plant main vent (other thin the wide range noble gas monitors), waste gas discharge, liquid waste processing discharge, condenser air removal discharge, steam generator blowdown tank discharge, steam generator blowdown recovery, and atmosphere (other than the control room ventilation and the containment isolation valves to the containment atmosphere monitors) are non-safety-related and do not perform any of the system intended functions based on 10 CFR 54.4(a)(1), (2), (3) and (b). Note that while the non-safety-related plant main vents radiatic, monitors are not in scope, the safety-related wide range effluent gas radiation monitors that monitor the plant main vents are in scope (see Figure 5.14-3 on page 5.14-6). Note also that while the non-safety-related containment atmosphere radiation monitors are not in scope, the containment penetration, including the safety-related containment isolation valves, are in scope (see Figure 5.14-4 on page 5.14-7).
NRC Ouestion No. 2 Section 5.14.1.2 states that the shaded areas of Figure 5.14-1 through 5.14-8 indicate which portions of the RMS are within the scope oflicense renewal. Figure 5.14-1 through 5.14 8 do not have sufficient illustration to explain which components the shaded areas represent. Provide a legend for Figures 5.14-1 through 5.14-8 that defines the components listed within them. Additionally, provide definitions for those acronyms used in these figures that are not already defined in other parts of your license application.
BGE Response Included below are !egends for the acronyms and symbols used in Figures 5.141 through 5.14 8.
Acronym Legend:
AE - Analysis lement(Sensing)
NO - Normally Open DL - Data Log foint PDT - Pressure Differential Transmitter E/E - Voltage to Voltage Signal Converter PI
- Pressure Indicator (Display)
E/I - Voltage to Current Signal Converter RE - Radiation Element (Sensing)
EFF - Effluent RI
- Radiation Indicator (Display)
FAI - Fails Asis RIC - Radiation Indicator (Controller)
FC - Fails Closed RR - Radiation Recorder (Display)
FIS - Flow Indication Switch SIAS. Saletyinjection Actuation Signal FO - Fails Open SV - Solenoid Valve FE - Flow E ement (Sensing)
TC - Temperature Controller FI
- FlowIndicator(Display)
TE - Element (Sensing)
FT - FlowTransmitter XI - Sample Timer (Display) 1
i ATTACHMENT (1) l RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION; INTEGRATED PLANT ASE.SSMENT REPORT FOR Tile RADIATION MONITORING SYSTEM i
l HS - Hand Switch ZS Position Switch MOV-Motor-Operated Valve IC10- Electric PanelIdentification NC - Normally Closed Number NDE-Normally De-Energized Symbol Legend:
l l
Y A High Efficiency ParticulMe
- Filter a N N N 4+
- vawes C Charcoal
- anu, cara c>ecx otose Sww l
o open I
HH. Very High
-[( ^ " ' $"
^
- Alarm Enunciator
-~q $ Nonne
.t g
LL - Very Low C Closed i
1.['y*---SERVICE --*M g
6'416#/
V5316A
- Instruments
- Motor Operated Valve
/
WSTRUMENT NO.
MS
- M LOCAL MOUNTED REMOTE MOUNTED l
l 1
1 FI
- Flow Gage
- Flow Orifice
- Drain Trap H H I
L l
im l
r, ControlValve 3
- Pump
- Pipe Cap l
N
- Hose Connection
'-~
- Pipe Reducer
- Drain Funnel l
--'O
- Quick Disconnect
)
- Conta.inment
- Data Log Point P pe Coupling Penetration
- Instrument Electrical
,//,,//
- Instrument Air X X X Tracing Electric Heat Line Line 2
l l
ATTACHMENT (1)
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION; INTEGRATED PLANT ASSESSMENT REPORT FOR TIIE RAcLATION MONITORING SYSTEM
[F
- Radiation Element
- Filter
- Microprocessor 1 - RE. 5317A
,.,s.34,3 NRC Ouestion No. 3 Are there any parts of the systems, structures, and components that are inaccessible for inspection? If so, describe what aging management program will be relied upon to maintain the integrity of the inaccessible areas. If the aging management program for the inaccessible areas is an evaluation of the inaccessible areas based on conditions found in st.rrounding accessible areas, please provide information to show that conditions would exist in accessible areas that would indicate the presence of or result in degradation to such inaccessible areas. If different aging effects or aging management techniques are needed for the inaccessible areas, please provide a summary to address the following elements for the inaccessible areas: (1) Preventive actions that will mitigate or prevent aging degradation; (2) Parameters monitored or inspected relative to degradation of specific structure and component intended functions; (3) Detection of aging effects before loss of structure and component intended functions; (4) Monitoring, trending, inspection, testing frequency, and sample size to ensure timely detection of aging effects and corrective actions; (5) Acceptance criteria to ensure structure and component intended functions; (6) Operating experience that provides objective evidence to demonstrate that the effects of aging will be adequately managed.
BGE Reponse All parts of the RMS at Calvert Cliffs that are within scope for License Renewal are accessible for testing and inspection, as needed, for managing the plaus"' sging effects.
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