ML20128P049
| ML20128P049 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 10/15/1996 |
| From: | Scott Flanders NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9610170123 | |
| Download: ML20128P049 (14) | |
Text
._
t October 15, 1996 ORGANIZATION:
Baltimore Gas and Electric
SUBJECT:
SUMMARY
OF MEETING WITH BALTIMORE GAS AND ELECTRIC COMPANY (BGE) ON BGE LICENSE RENEWAL ACTIVITIES On August 8.1996, the Nuclear Regulatory Commission (NRC) staff met with representatives of BGE in Rockville, Maryland, to provide comments to BGE revisions of the Main Feedwater, Structures IPA System and Commodity reports, and select examples of the Component Supports and Diesel Fuel Oil IPA System and Commodity reports submitted July 25, 1996.
These examples demonstrate BGE's implementation of the aging management and demonstration portion of the template.
A list of meeting attendees is provided in Attachment 1. is a copy F the material provided during the meeting.
During the meeting, the staff stated that during the review of the reports the it identified instances were BGE did not provide all of the information required by the template. is a matrix the staff preapred to compare the information in selected examples with the information required by the template.
This matrt was used to discuss the staff's comments.
BGE acknowledge that some of the examples needed to be revised to include all of the information required by the template.
BGE agreed to provide a discussion of the program elements and basis in future report revisions. The staff agreed that it is appropriate in some instances to reference the program elements and basis.
The staff and BGE also discussed the issue of operating experience.
The staff questioned why operating experience was not included in each of the examples.
BGE stated that the included operating experience in the examples where it beleived the operating experience was relevant to the aging management demonstration.
The staff and BGE agreed to discuss the issue of operating experience further.
Original signed by Scott C. Flanders, Project Manager License Renewal Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation l
Docket Nos..
50-317 and 50-318 Attachments:
1.
Attendance List 2.
Meeting Handouts f
cc w/ attachments: Distribution (see next page)
DFO\\ h i See next page DOCUMENT NAME: A:808MS (SFlanders/LLM Disk)
To credys a copy of this documentAdicate in the box: c = copy without attachment / enclosure "E" = Copy with attachment / enclosure "N" = No copy 0FFICE PM:PDLR M c
D:PDLRg $J l
NAME SFlandef$l SFNewb4rryf DATE
/0/ $ /96
/0 //l /96 0FFICIAL RECORD COPY 9610170123 961015 PDR ADOCK 05000317 NRC HLE CENTER COM r
~
October 15, 1996 eSEtog p
y
->k UNITED STATES s
j NUCLEAR REGULATORY COMMISSION 4"
WASHINGTON, D.C. 20665 4001
.....,o ORGANIZATION:
Baltimore Gas and Electric
SUBJECT:
SUMMARY
OF MEETING WITH BALTIM0RE GAS AND ELECTRIC COMPANY (BGE) ON BGE LICENSE RENEWAt. ACTIVITIES On August 8, 1996, the Nuclear Regulatory Commission (NRC) staff met with representatives of BGE in Rockville, Maryland, to provide comments to revisions of the Main Feedwater and Structures IPA System and Commodity reports, and select examples of the Component Supports and Diesel Fuel Oil IPA System and Commodity reports submitted July 25, 1996.
These examples demonstrate BGE's implementation of the aging management and demonstration portion of the template. A list of meeting attendees is provided in. is a copy of the material provided during the meeting.
The staff stated that during the review of the reports it identified instances where BGE did not provide all of the information required by the template. is a matrix the staff preapred to compare the information in selected examples with the information required by the template.
This matrix was used to discuss the staff's comments.
BGE acknowledged that some of the examples needed to be revised to include all of the information required by the template.
BGE agreed to provide a discussion of the program elements and bases in future report revisions.
The staff agreed that in some instances it is appropriate to reference the program elements and bases.
The staff and BGE also discussed the issue of operating experience.
The staff questioned why operating experience was not included in each of the examples.
BGE stated that it included operating experience in the examples where it beleived the operating experience was relevant to the aging management demonstration.
The staff and BGE agreed to discuss the issue of operating experience further.
/
'/
g/5' Sc'ott C. F nders, roject Manager License Renewal Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket Nos.:
50-317 and 50-318 Attachments:
1.
Attendance List 2.
Meeting Handout cc w/ attachments:
See next page l
October 15, 1996 i
Calvert Cliffs Nuclear Power Plant Baltimore Gas & Electric Company Unit Nos. 1 and 2 cc:
President Mr. Joseph H. Walter. Chief Engineer Calvert County Board of Public Service Commission of Commissioners Maryland 175 Main Street Engineering Division Prince Frederick. Md 20678 6 St. Paul Centre Baltimore. MD 21202-6806 D. A. Brune. Esquire General Counsel Kristen A. Burger. Esquire Baltimore Gas and Electric Company Maryland People's Counsel P.O. Box 1475 6 St. Paul Centre Baltimore, MD 21203 Suite 2101 Baltimore MD 21202-1631 Jay E. Silberg. Esquire Shaw. Pittman Potts and Trowbridge Patricia T. Birnie. Esquire 2300 N Street. NW Co-Director Washington. DC 20037 Maryland Safe Energy Coalition P.O. Box 33111 Mr. Terrence J. Camilleri. Director.
Baltimore MD 21218 NRM Calvert Cliffs Nuclear Power Plant Mr. Robert E. Denton 1650 Calvert Cliffs Parkway Vice President - Nuclear Energy Lusby. MD 20657-4702 Baltimore Gas and Electric Company Calvert Cliffs Nuclear Power Plant Resident Inspector 1650 Calvert Cliffs Parkway c/o U.S. Nuclear Regulatory Lusby. MD 20657-4702 Commission P.O. Box 287 Mr. Larry Bell St. Leonard MD 20685 NRC Technical Training Center 5700 Brainerd Road Mr. Richard I. McLean Chattanooga. TN 37411-4017 Administrator - Radioecology Department of Natural Resources 580 Taylor Avenue Tawes State Office Building 83 Annapolis MD 21401 Regional Administrator. Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia. PA 19406
October 15, 1996 DISTRIBUTION w/attactments-DISTR 18tfTION w/o attachments:
Central t nie/ Docket sile FMiragita/Alhadant 0412 bi6 PUBLIC R21 merman. 012 G18 PDLR R/F GHolahan. 0 8 E2MCase. 0-11 H21 8Sheron. 0 7 D26 bbTRIBlfTION via e-mail w/o attachnents:
TMartin. 0-11 H21 JMi tchell. tix) (JAM)
JCraig. RE5 (JnCl)
ACRS. T 2 E26 mayfield. RES (MEM2) JVora. RES (JPV)
Ptialsch. 0-15 818 AMurphy. RES (AJM1)
RWessman. NRR (R W )
TSpels. T-10 fl2 H8rrrner, NRR (HLB)
JStrosntder. NRR (JRS2)
EJordan, T 4 D18 RCorreta. NRR (RPC)
GMizuno. OGC (GSM)
JMoore/EHoller. 0 15 B18 POLR Staff SDroggttis, OSP (SCD)
OGC. 0 15 818 LShao. RES (LCSI)
CSerpar RES (CZS) 0Mathews. 0 10 H5 GBagcht. NRp (GX81)
RFrahm. Jr.
h,",P ( RE T ) RJonnsori. RES (REJ) l l
I 1
l l
I i
. _ _. ~.
ATTENDANCE LIST NRC MEETING WITH BALTIMORE GAS AND ELECTRIC COMPANY Auaust 8. 1996 i
NAME ORGANIZATION 1.
Scott Flanders NRR/DRPM/PDLR 1.
Barth Doroshuk BGE 2.
Don Shaw BGE 3.
A. lice Carson Bechtel 4
Tricia Heroux for EPRI S.
Barry Tilden BGE 6.
Marvin Bowman BGE 7.
John Moulton NRR/DRPM/PDLR 8.
Sam Lee NRR/DRPM/PDLR 9.
Scott Newberry NRR/DRPM/PDLR 10.
P.T. Kuo NRR/DRPM/PDLR l
1 l
Attactm mt #2 BGE Deliverable to NRC Enclosed August 8,1996
(
- 1. Portion of Radiation Monitoring System License Renewal Technical Report, written for LR Technical Report template Phase 2 development.
m
l For LR Technical Report Template Development August 8,1996 ATTACIIMENT (2)
APPENDIX A - TECIINICALINFORMATION 5.7 - OTIIER FLUID SYSTEMS 5.7.1 Area and Process Radiation Monitoring 1
5.7.1.1 Scoping i
System Description
l Provided later.
Sroped SCs and Their Intended Functions i
Provided later.
TABLE 5.7-1 l
l l
AREA AND PROCESS RADIATION MONITORING SYSTEM l
COMPONENT TYPES REOUIRING AMR Provided later 5.7.1.2 Aging Management The potential age-related degradation mechanisms (ARDMs) for the RMS are identified in Table 5.7-2.
Based upon system / component operating environment and component design, a number of these mechanisms were removed from further evaluation. These mechanisms are identified by a check mark
(/) in the "Not Plausible for System" column of Table 5.7-2. The plausible ARDMs are also identified in Table 5.7-2 by a check mark (/) in the appropriate column. Where no plausible age-related degradation was identified for a device type, no aging management is required.
For device types with identified plausible ARDMs, the following discussion provides the demonstration that the effects of the plausible aging are ari quately managed such that there will be reasonable assurance that the intended functions will be maintained consistent with the CLB during the period of extended operation.
RMS Pioing l
Provided later.
Control Valves - Materials and Environment The control valves in the Radiation Monitoring System that are subject to an aging management review are the containment penetration isolation valves for the containment atmosphere radiation monitor. The penetration configuration is such that one control valve is located inside the containment building, and the other control valve is located in the auxiliary building. The valve Application for License Renewal 5.7-1 Calvert Cliffs Nuclear Power Plant
For LR Technical Report Templ te Development Aug::.st 8,1996 ATTACIIMENT (2)
APPENDIX A - TECIINICAL INFORMATION 5.7 - OTIIER FL.UID SYSTEMS TABLE 5.7-2 POTENTIAL ANDlLAUSIBLE ARDMs Component Types for Which ARDM is Plausible Motor-Radiation Potential ARDMs Check Control Hand plow Flow Radiation d
Not Plausible Piping Operated Filter Test g
g gr Element Indicator Element a
f r System Point Cavitation Erosion
/
Corrosion Fatigue
/
Crevice Corrosion
/
/
Erosion Corrosion
/
Fatigue
/
Fouling
/
Galvanic Corrosion
/
General Corrosion
/
/
Hydrogen Damage
/
Intergranular Attack
/
/
Particulate Wear Erosion
/
Pitting
/
/
Radiation Damage
/
Rubber Degradation
/
Saline Water Attack
/
Selective Leaching
/
/
Stress Relaxation
/
Thermal Damage
/
Thermal Embrittlement
/
Wear
/
Application for License Renewal 5.7-2 Calvert Cliffs Nuclear Power Plant
l l.-
l l
l
[
For LR Technical Report Template Development August 8,1996 l
A_TTACHMENT (2) l l
APPENDIX A - TECIINICAL INFORMATION l
S.7 - OTIIER FLUID SYSTEMS j
body, bonnet, stem, seat and plug are constructed of Type 316 stainless steel material.
j L
i The process fluid to which the valves are exposed is the contairiment atmosphcre. The containment atmosphere conditions are approximately atmospheric pressure air at a maximum general area temperature of 120F and 70% relative hum'".ty.
The external environmental conditions are the auxiliary building atmosphere or the cont" iment building atmosphere.
Control Valves - Wear - Aping Mechani.sm l
These control valves are subject to wear of the valve seating surfaces due to cycling of the valve open and closed to support operation of the containment atmosphere radiation monitor. The effect of wear of the seating surfaces could be leakage past the valve seat. Valve seat leakage can result in the degradation of the containment pressure retaining boundary.
Control Valves - Wear - Method to Manage Aping The effects of valve seating surface wear can be managed by discovery of seat leakage through l
leakage testing. If unacceptable leakage is discovered, corrective actions would be performed in order to return the seating condition to within specified limits for leakage.
Control Valves - Wear - Aging Management Program The CCNPP Local Leak Rate Testing Program provides requirements for testing. containment penetrations and isolation valves in compliance with 10 CFR Part 50, Appendix J for Type B testing. The containment atmosphere radiation monitor control valves are within the scope of this program and are currently leak rate tested every two years (each refueling outage). This I
frequency of performance meets the currently accepted regulatory requirement for Type B testing. The testing checks for penetration component leakage at containment design pressure i
conditions. The acceptance criteria for the valves are conservatively set in order to ensure that l
containment leakage limits are not exceeded. If valve leakage is discovered that does not meet the acceptance criteria, corrective acti'>n is initiated to resolve the discrepant condition.
Control Valves - Wear - Demonstratian of Aging Management Based on the factors presented above, the following conclusions can be reached with respect to wear of the containment atmosphere radiation monitor containment isolation control valves:
The control valves support the containment isolation function and integrity must be maintained under CLB design conditions.
Wear of the valve seating surfaces is plausible for these control valves and could result in seat leakage which can lead to loss of containment pressure retaining boundary integrity.
The CCNPP Local Leak Rate Test Program provides requirements for periodic seat leakage testing for these valves in order to discover the effects of seating surface wear. The program Application for License Renewal 5.7-3 Calvert ClitTs Nuclear Power Plant
- ~.. _.
l l
i For LR Technical Report Template Development August 8,1996 ATTACIIMENT (2) l l
APPENDIX A - TECIINICAL INFORMATION 5.7 - OTIIER FLUID SYSTEMS requires the performance of corrective actions if acceptance criteria for leakage are not met.
This ensures that containment leakage limits are not exceeded.
Therefore, there is reasonable assurance that the effects of valve seating surface wear will be managed in order to maintain the containment pressure boandary~ integrity, consistent with the CLB, during the period of extended operation.
Iland Valves l
Provided later.
1 i
i Conclusion The programs discussed for the Radiation Monitoring System are listed in the following table. These
(
programs are (or will be for new programs) administratively controlled by a formal review and approval l
process. As demonstrated above, these programs will manage the aging mechanisms and their effects such that the intended functions of the Radiation Monitoring System will be maintained, consistent with the CLB, during the period of extended operation.
l Table 5.7-3 1
l LIST OF AGING MANAGEMENT PROGRAMS FOR TIIE FEEDWATER SYSTEM l
Program Credited As CCNPP Local Leak Rate Test Program Management of the effects of seating surface wear of l
Procedure " Local Leak Rate Test, containment atmosphere radiation monitor containment l
Penetrations 15. " STP M-571E-1/2 isolation control valves.
TABLE 5.7-4 LIST OF REFERENCES FOR TIIE AREA AND PROCESS RADIATION MONITORING SYSTEM Provided later.
4 Application for License Renewal 5.7-4 Calvert Cliffs Nuclear Power Plant
l Attachment #3 e
Program evaluations included in the matrix l
Feedwater1 l
component: Feedwater piping l
ARDM: Erosion / Corrosion Feedwater2 component: Feedwater piping i
ARDM: General Corrosion Structures component: Ground floor / Slabs, Basemats, Foundations & Walls (below grade); Intake Structure Fluid Retaining Walls & Slabs ARDM: Aggressive Chemical Attack on Concrete l
Comoonent Suonorts component: piping supports l
ARDM: General corrosion Diesel Fuel Oil I
component: Fuel Oil Storage Tank (Internal Surface)
ARDM: Crevice corrosion, general pitting, fouling, MIC l
l l
l
{
{
l I
4
.m
_..m._.._____
-... - _. _ _ _.-._-- _.... _.-.. - ~ __.
i i
i Template / Report Feedwater1 Feedwater2 Structures l Component Support h Diesel Fuel OE b
i l
lf l
Mitigation
/'
l j
/
/*
/
Discovery
/2 ja y
y i
[
j
- 4. Programs i
3 Existing / Modified /New l
Existing Existing N/A Existing Existing j
l i
h N/A l
- program name
/
/
/
/
ll l
l ll
- program purpose
/
/
N/A f
/
ll l
l l
l
- scope
/
/
N/A
/
l l
l l
l l
- bases N/A
/
l l
l l
l l
- developmental standards N/A
/
l l
l l
l
- references
/
/
N/A
/
- procedural steps l
ll ll
/
/
N/A
/
- technology ll ll ll l
N/A
/
j
- frequency or criteria for frequency l
l l
l N/A l
l l
l
- sample size / location N/A 3
l l
l l
- parameters monitored N/A
/
l l
l l
- acceptance criteria N/A
/
l l
l l
o corrective action confirmation N/A l
l l
l
- periodic verification N/A N/A N/A N/A l
l l
i
~
Template / Report l Feedwa5r1 l Feedwater2 l Structures l Component Support l Diesel Fuel Oil l
l l;
- operating experience l
N/A 1
Existing / Modified /New Existing New New/
Existing /New Existing h
Existing i
e program name h
l l
l h
ll
/
/
/
/
/
ll
)
l ll f
- program purpose
/
{
/
/
/
/
l l
l l
l l
l
- scope
/
/
/
/
/
l l
l l
l l
- bases
/*
/
/
l l
l l
l
- developmental standards
/*
/
l l
l l
l l
- references
/
/
/
ll
- procedural steps
/
/
/
/
3 l
achnology lf l
h l
l,
/*
/
i
- frequency or criteria for frequency l
l l
l l
l
/*
- sample size / location l
l l
l l
l f
/
l l
l l
l l
- parameters monitored
/
/
/
/
- acceptance criteria l
l l
l l
l
/$
/*
/
/
l l
l l
l l
- corrective action confirmation
/
- periodic verification l
l l
l l
l N/A N/A N/A N/A l
l l
l l
l
- operating experience
/
. e l
Notes 1, BGE did not specify which parameters are controlled.
- 2. Did not discuss how the methods detect the aging effect over a period of time in which there is reasonable assurance that detection will occur prior to the loss of the intended function under all l
CLB conditions (in Template Discovery Methods Second bullet-second sentence).
- 3. No discussion of what establishes the min wall value. (form Industry standard?)
- 4. The visual inspection program bases provided, however, no bases provided for PH program.
i
- 5. Does not specify the conditions that must be maintained.
j
- 6. Information for the follow up program for the 8 systems not covered by the ISI program needs to be provided.
l l
l l
l t
i I
t i
- -