Text

Environ Qualification of Safety-Related Equipment (IE Bulletin 79-01B), for Unit 2
	ML20004C178
Person / Time
Site:	Calvert Cliffs
Issue date:	11/12/1980
From:	Finkel A; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	;
Shared Package
ML20004C161	List: ML20004C167; ML20004C178;
References
	IEB-79-01B, IEB-79-1B, NUDOCS 8106010685
	Download: ML20004C178 (23)
	v • d • e

.-

ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRICAL EQUIPMENT IES79-01B TECHNICAL EVALUATION REPORT CALVERT CLIFFS 2 DOCKET NO. 50-318 DATED:

November 12, 1980 Licensee: 3altimore Gas and Electric Company Type Reactor: PWR, Combustion Engineering Size: 845 MWe' I

l Prepared by l

Alan E. Finkel Engineering Support Section Reactor Construction and Engineering Support Branch, RI 1

l 8106cio6T65 l

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Contents Page 1.

Introduction...............................................

1 1.1 General...............................................

1 2.

Background and Discussion........_............................

1 2.1 General...............................................

1 2.2 On-Site Verification Inspections......................

1 2.3 Eval uation o f Li censee's Report.......................

1 3.

General Information........................................

2 3.1 Identification of Class 1E Electrical Equipment.......

2 3.2 Service Conditions....................................

2 3.3 Quali fi cati on Documentation...........................

2

4. - Techni cal Eval uation v..?.~. cc.. c..... ;s.......................

2 4.1 Identification of Safety Related Equipment............

3

: 4. 2 ~ Ma s t e r L i s t...........................................

3 4.3 Service Conditions....................................

4 4.3.1 Inside Containment LOCA.....................

4 4.3.1.1 Radiation..............................

4 4.3.1.2 Submergence............................

4 l

4.3.1.3 Chemical Spray.........................

5 4.4 High Energy Line Breaks (HELB)........................

5 4.4.1 HELB Inside Containment.....................

5 4.4.2 HELB Outside Containment....................

5 4.4.3 Recirculated Fluids.........................

5 4.5 Margins...............................................

5 4.6 Aging........................................

6

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.I Table of Contents 2

Page 4.7 Documentation.........................................

6 4.8 Site Verification Inspection..........................

7 4.9 Equipment Data Review.................................

7 4.10 Conclusions..........................................

8 5.

Licensee Event Reports (LERs)..............................

8 6.

References.................................................

8 Appendix A, Test Reports and Analysis References............

Appendix B, Equipment Status Lists.........................

Appendix C, Licence's Evaluation's.........................

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INTRODUCTION 1.1 General i

The NRC Office of Inpection and Enforcement (I/E) issued Bulletion 79-01B, " Environmental Qualification of Class 1E Equipment" in January 1980.

This-bulletin required the licenses to prform a detailed evaluation of the environmental qualification on Class IE electrical equipment required to function under postulated accident conditions and to submit a report on this action.

This document is a report on the evaluation of the licensee's response to this bulletin.

2.

BACKGROUND AND DISCUSSION' 2.1 General The evaluation ofithe licensee's response was accomplished by performing an on-site inspection of selected class 1E equipment and by examining the licensee's report for completeness and technical accuracy.

The licensee's report used in this evaluation is dated October 31, 1980, and therefore, does not include the response to the bulletin supplement which was issuea cr. 9/30/80 in the form of Generic Questions and 4

Answers 1

2.2 On. Site Verification Inspections The on-site inspection, made on selected IE equipment, verified proper installation of equipment, overall interface integrity, and manufacturers nameplate data. The manufacturer and model number from the nameplate data was compared to information given in the Component Evaluation Work Sheets (CES) of the licensee's report.

If any discrepancies were noted between the installed equipment and the correspondence equipment addressed in the licensee's report, they are referenced in Section 4.8 of this report. The site inspection is documented by Report Number IE 50-318/80-18.

2.3 Evaluation of Licensee's Report Each component as addressed on the Component Evaluation Work Sheets

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(CES) of the licensee's report was examined for completeness and accuracy to the criteria given in the bulletin. This examination i

assumed qualification documents (analysis, test reports, etc.)

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referenced by the licensee in their submittal are acceptable.

2 i

i The results of this examination are documented in Appendix B.

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deneral Information 3.1 Identification of Class 1E Electrical Equipment The licensee's list of systems was compared to the systems list issued by the Environmental Qualification Branch (EQB) and discussed in Section 4.1 of this report.

It is recognized that there are differences in nomenclature of systems because of plant vintage and engineering design, therefore, many of these systems may not exist or have different titles. These differences will be addressed in the Safety Evaluation Report (SET) that will be prepared for this site.

3.2 Service Conditions The service condition accident environment, HELB/LOCA inside containment and HELB outside containment are indicated or discussed in the licensee's report and are. based on the FSAR accident analysis and Section 4.3 of this re, ort.

3.3 Qualification Documentation Appendix A is a list of documents (test reports, analysis, letters, etc.) used by the licensee in determining the environmental qualif-ication of plant equipment for Calvert Cliffs Nuclear Powe.- Plant, Uni,t 2.

These references have been tabulated by the licensee and are indicated on the applicable CES of their report.

4.

Technical Evaluation The basis for the technical evaluation is the information provided by the licensee, Baltimore Gas and Electric Company, for the Calvert Cliffs Unit 2 and the inspection of the as-installed equipment of the Compressed Air System which is located outside the containment.

(IE Inspection Report 50-318/80-18.

Utilizing the information identified above, the r9 viewer assessed its 4

6 adequacy in relation to the 00R guidelines, NUREG 0588, and the suoplements to IEB 79-018 which provides the Commission's requirements and staff positions.

i:

6 The gur.lity control measures utilized by the licensee included usir.g

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experienced consultants to perform the tasks required by IES79-018.

Independent technical overview of each part of the effort was performed by the licensee's engineering staff.

In addition, an extensive review of the final response and sign-off approvals by various levels of the licensee's engineering management was required.

O O

3 4.1 Identification of Safety-Related Equipment The licensee reviewed their docume.ntation to establish the systems required to achieve a safe shutdown or provide isolation for the events identified in IEB 79-018.

These systems were then evaluated against the DOR guidelines.

The systems identified and included in the evaluation are:

1.

Chemical and Volume Control 2.

Compressed Air (isolation. valves only) -

3.

Condensate and Feedwater 4.

' Containment Air Recirculation and Cooling 5.

Cooling Water 6.

Electrical 7.

Main Steami__

8.

Nuclear Heating 9.

Plant Heating (isolation' valve only) 10.

Radiation Monitocing 11.

Reactor Coolant-12.

Reactor Coolant and Waste Process Sample (isolation valves only) 13.

Safety Injection and Containment Spray 14.

Sampling (isolation valves only)

15. Ventilation

16. Waste Processing (isolation valves only) 1 The, list of systems including those that were excluded was provided to the Equipment Qualification Branch (EQB). 2The EQB compared the list to a "Q" list developed by the staff and to the lists provided by.similar facilities to determine the completeness of the licensee's response.

Basedontgeinformation.providedbythelicenseeandther'eviewers

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comparison, it has been determined that the systems identified are within the guidance provided in Section 3.0 and Appendix A of the 00R GJidelines and are acceptable with this exception.

1.

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be evaluated by the Equipment Qualification Branch (EQB) and addressed in the Safety Evaluation Report (SER) to be issued by February 1980.

4. 2 Master List The licensee developed a master list based on their system evaluation as required by IEB 79-018.

The licensee's 90 day response includes a list of references which provided the basis for including or excluding specific components / equipment from having a detailed data work sheet as required by IEB 79-018.

l l

4 The reviewer has reviewed the supporting basis for the inclusion or exclusion of equipment provided in the references and have con-luded that References dated March 6, 1980 and May 27, 1980 are acceptable except as noted in 4.1.

4.3 Service Condition 4.3.1 Inside Cont inment LOCA The licensee provided temperature and pressure values for the Calvert Cliffs Nuclear Power Plant Unit 1 containment resulting from a LOCA.

The licensee's 90 Day Response Report listed the maximum environments, but no profiles.

These values are listed below:

Temperature:

276 F Pressure:

50 PSIG Humidity:

100% R.H.

Chemical Spray:

1,700gPMBoricAcidSolution Radiation:

1 x 10 Rads The delay time from tae event to the initiation of safety injection for the spectrum of breaks is indicated in their FSAR profiles figures 14.16-4 and 14.16-6.

The licensee stated in their FSAR that the service conditions in the containment will return to the levels that existed prior to the event in less than 30 minutes.

4.3.1.1 Rediation 8

The 1 x 10 Radiation requirement listed by the licensee meets the 00R guidelines, Section 4.1.2.

The radiation levels calculated by the licensee are listed in the environ-mental charts of the licensee submitta13.

The reviewer has concluded that the radiation levels i

assigned by the licensee are within the gtaff's position in relationship to the second supplement to IEB 79-018.

4.3.1.2 Submergence 3

The licensee identified the components that are below the maximum expected flood level in containment, its location elevation, and their proposed action for each item.

The components listed below the flood level (16' - 4") are l

listed in Appendix B of this report.

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4.3.1.3 Chemical Spray The licensee stated that no chemical solutions are used in systems required for the accidents presently unt'er considera-tion. The consideration of chemical sprays is included in Section 4.9 of this report.

4.4 High Energy Line Breaks (HELB)_,

4.4.1 I!ELB Inside-Containment -

ThelicenseehasincludgdtheHELB.andLOCAvaluesaspart of their data submittal of October 31, 1980.

4.4.2 HELB Outside Containment The licensee is performing an analysis of the area outside contairment and will present the results of their evaluation in the-November 1, 1980 submittal.

The acceptability c f the licensee's basis for specific equipment subjected to-HELBs outside of containment cannot be evaluated at this time.

It is expected that a complate review will be made after the November 1, 1980 data submittal has oeen completed by the licensee.

4.4,.3 Recirculated Fluids The licensee indicated that both LOCA and HELB environments including areas where fluids are recirculated from inside l

containment to. accomplish long-term cooling following a l

LOCA have been listed in their April 23, 1980 submittg.

An up-date.was included in the May 22, 1980 submittal and 3

October 31,-1980 submittal 4.5 Margins The 00R Guidelines indicate that special consideration was given to the time raquired to remain functional when establishing the criteria in Section 5.2.of:the guidelines.

The, norma 1' operating temperature inside containment is approximately 120 F and the profiles indicate that the temperature returns to g

120 F within 27.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months of the event.

NUREG-0588, Section 3(4),

requires that a type test be for a minimum of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months in duration when the functional requirement is within the first seconds or minutes of an event and the DOR guidelines, Section 5.2, requires that the test duration be at least as long as the period from initiation

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until the service conditions return to the level that existed prior

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to the event.

3

6 Therefore, any type test that exceeds the functional operability time by 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or longer meets the requirements defined in NUREG-0588 i

and the D0R guidelines for margin in relation to test duration for this facility.

-The other consideration identified in the DOR guidelines in relation to the methods of qualification, other than identified specifically in this report will be addressed in the Safety Evaluation Report (SER) which will incorporate an audit of selected analysis and test reports identified in Appendix A.

4.6 Aging The licensee indicated that a study of the components subjected to harsh environments is still an outstanding item.3 Details of the licensee's effort is included in their submittal,

The licensee has identified the components which are still listed as requiring data.

The D0R guidelines, Section 7, does not require a qualified life to be established for all safety-related electrical equipment, however, the following actions are required:

1.

Detailed comparison of existing equipment to the materials identified in Appendix C of the 00R guidelines. The first 4

l supplement to IEB 79-018 requires the licensees to utilize the l

table and identify any additional materials as the result of their effort.

l 2.

Establish an ongoing program to review surveillance and maintenance records to identify potential age related degradations.

3.

Establish component maintenance and replacement schedules which include considerations of aging characteristics of the installed components.

10 l

The licensee has stated that the aging study is still in progress We therefore, require that the licensee provide the details of a program which will include a continuing effort to obtain data on existing materials and address the actions identified above.

In addition, we require the licensee provide a schedule for implementaton of the program that identfies problem components.

4.7 Documentation 4

5 The second supplement to IEB 79-01B and the order, No. CLI-80-21, requires the licensee have the documentation and data identified in the detailed worksheets which supports the qualification of the

7 safety related eigetrical equipment available for NRC audit.

The second supplement identifies the type of information required and the locations where the. records are to be maintained.

The licensee has provided a response to the order and supplement which discusses their compliance and identifies any deviations, reference Appendix

-B of this report.

4.8 Site Verification Inspection An inspection of-the installed components associated with the Compressed Air System was conducted on October 27-29, 1980, at the Calvert Cliffs 2 facility. The details of this inspection are documented in IE Inspection Report 50-318/80-18.

The detailed identification of the components and the observations recorded will be: addressed in the SER which will incorporate an audit of selected analysis and test reports identified in Appendix A.

4.9 Equipment Data Review The equipment listed in Appendix B is the status of the latest data submittedby.the-licenseeintgeieresponsetoIEB79-018: Appendix B identifies therlicensee data in a format that allows the reviewer a quick look status of each listed component.

The first four columns are self explanatory while the next three columns are defined as follows:

y.

Environment - The listing in this column identifies the environment that+ appears to have some question as to whether or not its'in noncompliance with the requirements of the licenee.

Category - As listed below a Category I through:V :has been assigned to the environment for a specific component or group of components as listed.

+.

Remarks - The remarks column was used to identify the: environ-mental ccidition associated with the category number, or identify the system location when the licensee indicated that data was being looked for or an analysis was in progress.' 'An: example'of this lack of data environment information in the licensee submitall is the requirement for aging.

The equipment has been listed and identified in one of.the+folicwing categories:

I Qualified for Plant Life II Qualified With Restrictions III Exempted From Qualification IV Qualification of Equipment Unresolved, and V Equipment Not Qualified The number in the ( ) in the component block on the table indicates the number of identical components listed, but may have a different title within the report.

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8 4.10 Conclusion l

This evaluation is based on the on-site inspection, the information supplied by the licensee in their IEB 79-018 submittal, their FSAR, and the assumption that the Qualification Documentation (Test Reports, Analysis, Letters, etc.) are acceptable.

1 0

The Region I reviewer using the guidance and instructions, for the evaluation of licensees data submittals and the site verification l

inspections that were performed to verify the IE Bulletin 79-01B, January 1980 data, submittal informaggn, finds the licensee to be in accordance with the NRC direction except as listed in Appendix B and C of this report.

The results of this evaluation uoes not necessarily imply that the l

equipment is unreliable, unsafe or represents a significant safety issue; it does imply that additional information is required and that the items in Appendix B and C will be evaluated by the Equipment i

Qualification Branch (EQB) and addressed in the Safety' Evaluation t

l Report (SER) to be written for this license by February, 1981.

l S.

Licensee Event Reports (LERs)

No licensee event reports were submitted by the licensee, associated with l

their evaluation of IEB 79-01B, as of October 31, 1980.

6.

References 1.

IEB 79-018, Memo to V. Thomas (NRC) from A. Finkel (NRC) dated August 18, 1980.

2.

EQ Branch Comparison of systems and parameters.

(Systems List CE PWR) 3.

Baltimore Gas and Electric Company, Revised and Updated Response to l

IEB 79-013, dated October 31, 1980.

4.

Supplement Information to IEB 79-018, dated February 29, 1980, and September 30, 1980 and October 24, 1980.

l 5.

Order requiring licensees implement requirements of Commission Memorandum and Order of'May 23, 1980 (CLI-80-21).

6.

Division of Operating Reactors (DOR), " Guidelines for Evaluating Environmental Qualification of Class IE Electrical Equipment in Operating Reactors", Enclosure 4 to IEB 79-018.

7.

NUREG-0588, " Interim Staff Position on Environmental Qualification of Safety Related Electrical Equipment", dated December 1979.

1 l

9 8.

Inspection Requirements for Verifying Reactor Licensee Responses to IE Bulletin No.79-01B, dated April 25, 1980.

9.

IE Support and Review of Environmental Qualification of Electrical Equipment at Operating Reactors, dated October 10, 1980.

10.

Baltimore Gas and Electric Company, Responses to IEB 79-01B dated March 3,1980, March 5,1980, April 17,1980, May 22,1980 and October 31, 1980.

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o APPENDIX A

Test Reports and Analysis References l

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Masoneilan Simulation LOCA Test Report 2.

Specification M-293 3.

Correspondence with TATE Engineering 4-29-80, 5-19-80 (Radiation = 200 E + 6) 4.

FSAR Section 5 and 14.15 for LOCA 5.

Radiation Zones Reference Drawir.s A-105 and 106 6.

N0/FC Technical Specification 3/4.6.4 I

7.

ASCO Test Report AQS-21678/TR 8.

Reactor Shielding Design Manual; Table 10.1 9.

Limitorque Test Report 600456 12-9-75 10.

FSAR 10A.1-16 Main Steam Line Break 11.

F and P Test Report 2204-51-8-006 12-68; Seismic 9-71 12.

FIRL Test Report F-C2815 5-70; e of c 9-71, 10-71 and 11-71 13.

American Air Filter Co. Test Report 4-7-73

14. Mechanical Calculation 8-2-5, Temperature = 120 F 15.

FIRL Test Report F-C2525 10-69 16.

FIRL Test Report F-C4350 7-76 17.

Okonite Summary of FIRL Test Report 5-77 18.

BIW Test Report No. 9299 11-72 19.

FIRL Test Report F-C2935 20.

BIW Test Report No. 73C212 21.

FIRL Test Report F-C2750 3-70 22.

FIRL Test Report F-C2442 4-69 23.

FIRL Test Report F-C2781 3-70 24.

Hatfield Report 2-70 25.

ETD Report No. 16024 26.

Amphenol Sams Test Report No. 123-1252 6-74 27.

ReferenceE-406DesignandCgnstructionStandard 28.

FSAR 10A.3-4 Rev Tmax of 212 F with/SG Building Line Break 29.

F&P Radiation Summary Report DP2224-1 #004 11-73 30.

GULF Test Report E115-138 12-71 and c of c 10-4-71 31.

Bechtel Letter 5-22-73; Velan c of c 5-2-73 32.

Seismic Calculation 12-18-69 33.

G.E. Performance Data 7-8-69 i

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APPENDIX B

Equipment Status References l

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l The following notes are referenced in the remakrs column of the equipment status listing.

NOTES:

1.

Fisher and Porter Transmitters - will be replaced due to the difficulty in obtaining the replacement parts required to maintain the qualifiction of this equipme it.

To be completed during the Unit 1 Cycle 6 and Unit 2 Cycle 5 refueling outages.

2.

Asco Solenoid Valves - valves for which adequate documentation does not exist will be replced with fuily qualified valves. To be completed during the 1980 :sfueling outage.

3.

Raychem Cable - require further information on humidty from vendor.

To have resolved by January 1, 1981.

4.

Amphenol Connectors - Evaluating qualification test program.

T.o be completed by June 1, 1982 concurrent with nuclear instruments.

5.

Bendix Connectors - Evaluting qualification test program.

To be completed by June 1,1982 concurrent with nuclear instruments.

6.

ITT Cannon Connectors - Evaluating qualification test program.

To be completed by June 1, 1982 concurrent with nuclear instruments.

7.

Kinas Connectors - Evaluating qualification test program. To be completed by June 1, 1982 concurrent with nuclear instruments.

8. ' Republic /Teledyne Solenoid Valves - Require further information from vendor on temperature and radiation.

To be resolved by January 1, 1981.

l 9.

Westinghouse Fission Chambers - C-E users group evaluating new component design.

10. Westinghouse Radiation Monitor - Require further information from vendor.

To have resolved by January 1, 1981.

11.

Rosemont RTD - Cannot obtain sufficient qualification data. To be replaced during the Unit 1 Cycle 6 and Unit 2 Cycle 5 refueling outages.

12.

Dragon Solenoid Valve - Cannot obtain sufficient qualification data.

To be replaced next scheduled outage after January 1, 1981.

l The licensee stated that records and test data concerning the environmental qualification of Class 1E electrical equipment are being maintained separate from the Plant History File.

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F APPENDIX C

Licensee Exceptions 4

+

Th'.

>11owing licensee response addresses the safety related equipment located in in..sh environments including that required for cold shutdown.

The non-safety related additional cold shutdown equipment located in harsh environments and the safety related equipment installed as a result of the TMI Action Plan will be submitted by February 1,1981 as directed in IE Bulletin No. 79-018 Supplement No. 3".

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