ML18152A234

Requests Exemption from 10CFR50,App J Section III.D.3 Re Local Leak Rate Testing During Every Reactor Shutdown. Basis & Justification for Exemption Encl

ML18152A234
Person / Time
Site:	Surry
Issue date:	09/14/1990
From:	STEWART W L VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
90-570, NUDOCS 9009240102
Download: ML18152A234 (27)

Text

• -,.* e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 September 14, 1990 United States Nuclear Regulatory Commission Attention:

Document Control Desk Washington, D. C. 20555 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 10 CFR 50 APPENDIX J EXEMPTION REQUEST ... Serial No.90-570 NO/ETS Docket No. 50-281 License No. DPR-37 In accordance with 1 O CFR 50.12, we are requesting a one time exemption from 1 O CFR 50, Appendix J, Section 111.D.3, for Operating License DPR-37 Surry Unit 2. Section 111.D.3 of Appendix J requires Local Leak Rate Testing (LLRT) during every reactor shutdown for refueling but in no case at intervals greater than two years. Surry Unit 2 was shutdown for refueling on September 10, 1988 and remained in the refueling outage for 374 days to perform maintenance and modifications

.. Because of this extended outage the Type C testing requirements of 1 O CFR 50 Appendix J will be due for performance prior to the scheduled refueling date (April 5, 1991 ). This is based on an interpretation that the interval requirement is applied individually to each applicable valve. -We are requesting a one-time extension to perform the LLRT testing at the scheduled Cycle 1 O refueling outage. As a result of a recent Quality Assurance audit of the lnservice Inspection program, we have discovered that our implementation of the Type C testing program could allow individual containment isolation valves to be tested at greater than two year intervals.

Our previous interpretation has been that the interval is initiated upon completion of the Type C periodic test procedure which includes every valve under the purview of this requirement.

An assessment of the Surry Unit 2 Type C tests performed during the extended outage (September 1988 to September 1989) was performed subsequent to the QA Audit. It was determined that certain containment isolation valves, which passed their Type C testing, will exceed the two year interval before the next refueling outage based on the individually applied test interval interpretation.

The two year interval expires on September 18, 1990 for the first valves tested. In order to eliminate a Unit 2 shutdown during the operating cycle just to perform the Type C testing, we are requesting this exemption.

The affected valves are currently operable and, based on the projected leak rates, will remain operable through June 1991. Therefore, due to the recent nature of this interpretational discrepancy, we request that we not be cited for non-compliance with the Code or our Technical Specifications pending processing and resolution of this request and a forthcoming Technical Specification change. This exemption request has been reviewed and approved by the Station Nuclear Safety and Operating Committee.

It has been determined that the proposed exemption does not involve an unreviewed safety question as defined in 1 O CFR 50.59. f/011 1/ I

-. The basis and justification for this exemption are contained in Attachment

1. Very truly yours, W)L~ W. L. Stewart Senior Vice President

-Nuclear Attachments

1. Appendix J Exemption Request 2. Unit 2 Type C Test History cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W. Suite 2900 Atlanta, Georgia 30323 Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station / _j

... ATTACHMENT 1 SURRY POWER STATION UNIT 2 10CFR50 APPENDIX J TYPE C TESTING EXEMPTION REQUEST

... DISCUSSION 10 CFR 50, Appendix J requires that Type C tests be performed "each reactor shutdown for refueling but in no case at intervals greater than 2 years." At Surry Power Station, this interval requirement has been interpreted to initiate at the completion of the Type C periodic test procedure which tests every valve which falls under the purview of the rule. The two year interval requirement has not been interpreted as applying individually to each valve. BACKGROUND In letters dated January 8, March 20 and April 20, 1990, we requested and were granted an extension for Surry Unit 1 to perform local leak rate testing at the Cycle 1 O refueling outage scheduled for October 1990. A Unit 2 extension request was not requested at that time based on our interpretation that the two year inspection interval was initiated at the end of the overall Type C periodic test rather than applied individually to each valve. We were not aware of any specific NRC guidance which had been issued as to application of the inspection interval to individual valves. At last week's exit interview of a recent Quality Assurance audit of our lnservice Inspection program, the issue of our interpretation of the two year interval was raised by an outside expert participating in the audit. Based on this interpretation concern, an immediate review was undertaken to assess any impact with respect to Surry Unit 2. It was determined that seventy-six valves would be impacted by this individual valve interval interpretation.

In subsequent telephone discussions on September 13, 1990 with the NRC staff, we were informed that the Type C inspection interval applied to individual valves and not to the aggregate Type C test. Based on the NRC position, our previous determination for Unit 2 Type C testing requirements is incorrect and a one time exemption request in the form of a schedule extension is requested to avoid an unnecessary mid-cycle outage. Surry Unit 2 was shutdown for refueling on September 10, 1988. Local Leak Rate Testing (Type C testing) commenced in September 1988 and was completed in September 1989. Due to the extended refueling and maintenance outage, the next refueling outage is currently scheduled for the second quarter 1991. The interval between the refueling outages will exceed the two year requirement of Appendix J for the valves tested early in the extended outage. As stated in 1 O CFR 50, Appendix J, Section Ill. D.3, local leak rate testing shall be performed during reactor shutdowns for refueling but in no case at an interval greater than two years. Therefore, an exemption to this Appendix J requirement in the form of a one-time extension of the interval is being requested.

The Surry Unit 2 refueling outage is currently scheduled to commence April 5, 1991 and the refueling

'as-found' Local Leak Rate Testing (LLRTs) could be completed in approximately 4 weeks from that date, barring any unforeseen scheduling difficulties.

However, due to the uncertainties associated with the start of a refueling, we are requesting an exemption until June 30, 1991 to complete the LLRTs.

.. ' The test interval would be extended approximately 9 months if June 30, 1991 is used for the exemption.

This date would not exceed two years of power operation on any of the penetrations.

There are a total of 122 containment isolation valves and 63 penetrations.

An exemption is required for 76 valves associated with 42 penetrations.

Those valves associated with safety systems and safe operation of the plant cannot be tested without rendering the system or train inoperable for a period greater than Technical Specifications would permit. Auxiliary systems (i.e., sampling, leakage monitoring, steam generator recirculation and transfer, vent and drain, service air, fire protection, and reactor cavity purification systems) could be tested. However, unless containment entries were made only the outside valves could be tested and only limited venting and draining of the penetrations could be accomplished.

If the unit was forced to cold shutdown and atmospheric conditions were established prior to the scheduled refueling outage, an average of 5 penetrations (approximately 1 O valves) could be tested each day. This number is approximate and depends on the circumstances of the forced shutdown and existing plant conditions.

TECHNICAL BASIS The following presents the 1986 and 1988 Type C leakage results for the valves included in the exemption request. A projection of the 1990 Type C test results based on the 1986 and 1988 test results and the maintenance history of the valves is also included.

1986 Type C Test Results (Exemption Request Valves) 'As-found' Total: 925.663 SCFH Major contributors were: TV-DA-200A/B, TV-CH-2204, FCV-CH-2160, MOV-RS-256A, and 2-VP-12. Both penetrations 38 (TV-DA-200A/B) and 46 (FCV-2160) had 300 SCFH leakage rates. Penetration 28 (CH-2204) had a 169 SCFH leakage rate. TV-DA-200A/B and CH-2204 have been replaced.

FCV-2160 is water filled and not considered a credible leakage path. These valves were repaired and retested satisfactorily as demonstrated by the test results in Attachment

2. 1988 Type C Test Results (Exemption Request Valves) 'As-found' Total: 110.256 SCFH Major contributors were: 02-RS-11, MOV-RS-256A, 02-VP-12.

These valves were repaired with satisfactory

'as-left' results as noted in Attachment

2.

1991 Projected Type C Test Results (Exemption Request Valves) 'As-found' Total: 42.436 SCFH The projected value is based on 76 valves. For each valve a projected leakage calculation was performed and then the projected leakage for the 76 valves was totalled.

If a valve had a negative leakage trend, the most recent 'as-found' leakage value was used. For valves that were overhauled or replaced, the most recent post-maintenance

'as-found' leakage value was used. If the 'as-found' leakage was not available, then the 'as-left' leakage value was used. Projected Leakage Calculation Methodology If: then: 1) 2) 3) 4) Test 1 = Test 2 = LRTM= 23 months= 33 months= PVLI = 1986 'as-found' test results 1988 'as-found' test results Leakage Rate Trend Month Elapsed time between 1986 and 1988 tests Time between 1988 test and June 1991 Projected Valve Leakage Increase (Test 2 -Test 1) = LRTM -----23 months LRTM x 33 months = PVLI Test 2 + PVLI = Projected 1991 leakage for that valve 76 I, (Test 2 + PVLI) = Projected 1991 leakage for valves included in the 1 exemption request 1991 Projection for Type C test results 91.521 SCFH This includes all 122 valves using 1986 and 1988 'as-found' data and projection out to June 30, 1991. CONCLUSION The subject valves are considered to be leak tight and in good material condition.

We conclude based on the improved maintenance history of the subject valves and projected leakage rate, that an extension to June 30, 1991 will not impair continued valve operability or significantly degrade leak tightness.

e e .. . LEAKAGE PROJECTION TO JUNE 30, 1991 FOR EACH PENETRATIONS PROJECTED PROJECTED PEN NO LEAKRATE (SCFH) PEN NO LEAKRATE (SCFH) 7 5.77 58 0.51 15 0.271 60 3.05 19 0.26 61 0.69 20 0.0 62 10.65 21 0.3 63 0.506 23 0.212 64 0.9 24 0.955 66, 67 0.526 28 0.022 68, 69 1.0 32 0.0 70 0.693 33 0.67 71 8.316 38 0.175 89 6.6 42 0.06 90 7.88 43 0.091 91 17.11 44 0.0 92 1.12 45 0.0 93 0.809 46 16.05 94 0.95 47 0.067 978 0.0 48 0.0 97C 0.0 50 0.74 100 0.0 51 0.056 101 0.0 53 3.08 103 0.0 54 0.146 104 0.0 550 0.0 1058 0.0 56A 0.0 105C 0.0 568 0.025 106 0.0 560 0.0 112 0.22 57A 0.0 113 0.231 578 0.57 57C 0.0 570 0.24

"* -JUSTIFICATION 10 CFR 50.12 states that the Commission may grant exemptions from the requirements of the regulations contained in the 10 CFR 50 provided that: (1) the exemption is authorized by law, (2) the exemption will not present an undue risk to the public health and safety, (3) the exemption is consistent with the common defense and security, and (4) special circumstances as defined in 1 O CFR 50.12(a)(2) are present. 1. 2. The Reguested Exemption is Authorized by Law No law exists which would preclude the activities covered by this exemption request, thus the Commission is authorized to grant this exemption.

The Requested Exemption Does Not Present an Undue Risk to the Public Health and Safety 1 O CFR 50 Appendix J states that the purpose of the regulation is to assure that leakage through primary containment does not exceed allowable values, as specified in the Technical Specifications, and that proper maintenance and repairs are performed throughout the service life of the containment boundary components.

The requested exemption is consistent with the purpose of the regulation and the intent of the two year LLRT testing rule. The exemption requests a one-time extension until the Cycle 1 O refueling outage when containment integrity is not required.

The refueling outage is currently scheduled for the second quarter of 1991. The LLRTs shall be performed during reactor shutdown, as required, to assess compliance with the Technical Specification allowable leakage values and assure that any required maintenance or repairs are performed.

The intent of Section 111.D.3 of Appendix J is to assure containment integrity.

Based upon the following information, the requested exemption will not significantly impact the ability of primary containment to contain post-accident leakage to within Technical Specification limits, as required.

a. Our LLRT Program has undergone significant changes and improvements.

In the 1986-1988 timeframe we increased efforts to minimize Type C leakage by improving test procedures and methods, conducting supplemental LLRTs on penetrations that have been poor performers, and making modifications to selected penetrations.

The latest Type B and C test results are currently 22.085 SCFH where 0.6 La is 180 SCFH. b. Since the LLRTs were conducted on the components during the last refueling outage (September 1988 -September 1989) the plant has operated for approximately twelve months. Therefore, the actual service period during power operation for the containment isolation valves, including the projected seven months until the Surry Unit 2 outage, will be less than the two-year maximum allowable interval.

The remaining calendar time betwen component testing will have occurred during periods of cold shutdown which are considered to be less severe service conditions than power operations.

3. 4. c. As referenced in our Technical Specifications, primary containment integrity and compliance with the allowable leakage rates may be relaxed when the reactor is in the cold shutdown condition.

We interpret this to mean that an exemption would not be necessary in the event that components subject to Type C tests are not tested within the two years, if the interval expires during cold shutdown and the tests are completed prior to restart. The Reguested Exemption Will Not Endanger the Common Defense and Security The common defense and security are not an issue in this exemption request. Special Circumstances are Present Which Necessitate the Reguest for an Exemption to the Regulations of 1 O CFR 50 Appendix J, Section 111.D.3 Per 1 O CFR 50.12(a)(2), the following special circumstances are present: a. Application of the regulation in the particular circumstances would not serve the intent of the regulation.

The intent of the regulation is to assure containment integrity through valve performance.

The actual in-service period during power operation for the containment isolation valves, including the projected seven months until the Surry Unit 2 outage, will be less than the two-year maximum allowable interval.

The remaining calendar time betwen component testing will have occurred during periods of cold shutdown which are considered to be less severe service conditions than power operations.

Furthermore, projected leakage values indicate the expected valve performance would not exceed 0.6 La requirements.

Thus the time requested does not conflict with the intent of the regulation, and deferring the Appendix J LLRT requirements until the next scheduled refueling outage in second quarter of 1991 is appropriate.

b. Compliance with the regulation would result in undue hardship or other costs that are significantly in excess of those contemplated when the regulation was adopted. The intent of the regulation is that the required testing be performed during normal refueling outages, to ensure containment integrity.

A requirement for shutdown to comply with the year testing requirement, even though the projected leakage is considerably less than requirements, would result in undue hardship and excessive costs in the form of lost revenues due to plant shutdown, and higher costs associated with two outages rather than one. Increasing the LLRT testing interval in this case also eliminates one heatup and cooldown cycle and lowers the probability of events which are more likely during such plant evolutions.

c. The exemption would provide only temporary relief from the applicable regulation and we have made a good faith effort to strictly comply with the regulation.

The exemption being requested is a one-time exemption (until the second quarter of 1991) for the LLRT testing requirement due to the extended refueling/maintenance outage during Cycle 10. The request is not the result of negligence on our part as we have always performed the test consistent with our interpretation of interval initiation during refueling outages as intended by the regulation.

In fact, this request is the result of our response to a self-identified issue. If Unit 2 was forced to cold shutdown and to establish atmospheric conditions prior to the scheduled refueling outage, Type C testing of containment isolation valves would be performed at a rate consistent with that identified in the above discussion for approximately two weeks. SAFETY IMPACT Virginia Electric and Power Company has reviewed this exemption and determined that extending the test interval of the subject containment isolation valves will not impact nuclear safety. This exemption request provides a one-time extension of the two-year interval for Appendix J LLRT testing requirements.

Thus, operation of the Surry Power Station in accordance with the proposed changes will not: 1. Involve a significant increase in the probability of occurrence or consequences of any accident or malfunction of equipment which is important to safety and which has been evaluated in the UFSAR because extending the LLRTs does not affect the probability of occurrence of accidents, nor will projected degradation of equipment occur that would change the consequences of an accident.

The exemption request is consistent with the intent of the regulation.

2. Create the possibility of a new or different type of accident from those previously evaluated in the safety analysis report. Physical plant modifications are not being made and plant operations are not being changed. Consequently the systems' ability to perform its intended function will be maintained, no new accident precursors are being generated and therefore no new or different kind of accident is created. 3. Involve a significant reduction in the margin of safety. Plant operations are not being changed nor are any of the accident analysis assumptions being modified or exceed by this change. The deferral of the LLRTs will not result in significant degradation of equipment in that the equipment will be in service for about the same time as a normal 18 month operating cycle. The projected leakage rate (92 SCFH) is well below the 0.6 La (180 SCFH) acceptance criterion.

Therefore, the accident analysis assumptions remain bounding and safety margins remain unchanged.

ATTACHMENT 2 SURRY UNIT 2 CONTAINMENT ISOLATION VALVE TYPE C TEST HISTORY SURRY UNIT 2 CONTAINMENT ISOLATION VALVE TYPE C TEST HISTORY TEST MEASUREMENT PEN NO VALVE NO TEST DATE (SCFH) 007 2-Sl-0150 10/06/86 17.150 007 2-Sl-0150 11/17/86 31.000 007 2-Sl-0150 11/24/86 1.000 007 2-Sl-0150 03/30/88 6.400 007 2-Sl-0150 04/02/88 3.740 007 2-Sl-0150 09/12/88 5.770 007 2-Sl-0150 09/04/89 0.000 007 MOV-S l-2867C 10/06/86 17.150 007 MOV-S1-2867C 11/17/86 31.000 007 MOV-S l-2867C 11/24/86 1.000 007 MOV-S l-2867C 03/30/88 6.400 007 MOV-S1-2867C 04/02/88 3.740 007 MOV-S1-2867C 09/12/88 5.770 007 MOV-S1-2867C 09/04/89 0.000 007 MOV-Sl-2867D 10/06/86 17.150 007 MOV-S l-2867D 11/17/86 31.000 007 MOV-Sl-2867D 11/24/86 1.000 007 MOV-S l-2867D 03/30/88 6.400 007 MOV-Sl-2867D 04/02/88 3.740 007 MOV-Sl-2867D 09/12/88 5.770 007 MOV-S l-2867D 09/04/89 0.000 015 2-CH-0309 10/12/86 0.220 015 2-CH-0309 09/22/88 0.241 015 MOV-CH-2289A 10/12/86 0.330 015 MOV-CH-2289A 11/17/86 0.240 015 MOV-CH-2289A 11/26/86 0.120 015 MOV-CH-2289A 12/21 /87 0.200 015 MOV-CH-2289A 05/26/88 0.260 015 MOV-CH-2289A 05/28/88 0.239 015 MOV-CH-2289A 09/22/88 0.208 015 MOV-CH-2289A 07/13/89 0.172 015 MOV-CH-2289A 09/03/89 0.072 SURRY UNIT 2 CONTAINMENT ISOLATION VALVE TYPE C TEST HISTORY TEST MEASUREMENT PEN NO VALVE NO TEST DATE (SCFH) 019 MOV-CH-2381 10/08/86 0.000 019 MOV-CH-2381 10/26/86 0.000 019 MOV-CH-2381 09/27/88 0.107 019 MOV-CH-2381 07/03/89 0.000 019 MOV-CH-2381 07/05/89 0.000 020 2-Sl-0032 10/06/86 0.000 020 2-Sl-0032 09/18/88 0.000 020 2-Sl-0032 10/24/88 0.000 020 2-Sl-0032 12/06/88 0.000 021 MOV-Sl-2842 10/05/86 0.250 021 MOV-Sl-2842 11/17/86 8.700 021 MOV-Sl-2842 09/11 /88 0.151 021 MOV-Sl-2842 07/22/89 0.300 023 MOV-S 1-2869 B 10/05/86 0.173 023 MOV-Sl-2869B 11/17/86 0.000 023 MOV-Sl-2869B 09/12/88 0.189 023 MOV-Sl-2869B 09/03/89 0.137 024 MOV-RH-0200 10/10/86 0.225 024 MOV-RH-0200 09/26/88 0.525 028 HCV-CH-2200A 06/21 /86 8.880 028 HCV-CH-2200A 10/15/86 18.660 028 HCV-CH-2200A 11/17/86 0.000 028 HCV-CH-2200A 12/09/87 109.860 028 HCV-CH-2200A 12/14/87 0.000 028 HCV-CH-2200A 09/29/88 0.022 028 HCV-CH-2200A 01/20/89 0.000 SURRY UNIT 2 CONTAINMENT ISOLATION VALVE TYPE C TEST HISTORY TEST MEASUREMENT PEN NO VALVE NO TEST DATE (SCFH) 028 HCV-CH-22008 06/21/86 8.880 028 HCV-CH-22008 10/15/86 18.660 028 HCV-CH-22008 11/17/86 0.000 028 HCV-CH-22008 12/09/87 109.860 028 HCV-CH-22008 12/14/87 0.000 028 HCV-CH-22008 09/29/88 0.022 028 HCV-CH-22008 01/20/89 0.000 028 HCV-CH-2200C 06/21 /86 8.880 028 HCV-CH-2200C 10/15/86 18.660 028 HCV-CH-2200C 11/17/86 0.000 028 HCV-CH-2200C 12/09/87 109.860 028 HCV-CH-2200C 12/14/87 0.000 028 HCV-CH-2200C 09/29/88 0.022 028 HCV-CH-2200C 01/20/89 0.000 028 TV-CH-2204 10/15/86 169.340 028 TV-CH-2204 11/17/86 0.000 028 TV-CH-2204 12/09/87 0.000 028 TV-CH-2204 09/29/88 0.000 028 TV-CH-2204 01/20/89 0.000 028 TV-CH-2204 07/16/89 0.000 028 TV-CH-2204 09/30/89 305.000 028 TV-CH-2204 10/01 /89 0.220 032 TV-GW:-0202 10/10/86 0.000 032 TV-GW-0202 09/23/88 0.000 032 TV-GW-0203 10/10/86 0.000 032 TV-GW-0203 09/23/88 0.000 033 TV-DG-0208A 10/08/86 0.090 033 TV-DG-0208A 11/17/86 0.040 033 TV-DG-0208A 10/25/88 0.220 033 TV-DG-02088 10/08/86 0.860 033 TV-DG-02088 11/17/86 0.900 033 TV-DG-02088 10/25/88 0.670 SURRY UNIT 2 CONTAINMENT ISOLATION VALVE TYPE C TEST HISTORY TEST MEASUREMENT PEN NO VALVE NO TEST DATE (SCFH) 038 TV-DA-0200A 10/08/86 300.000 038 TV-DA-0200A 11/17/86 0.000 038 TV-DA-0200A 12/10/87 0.000 038 TV-DA-0200A 10/13/88 59.000 038 TV-DA-0200A 11/10/88 0.170 038 TV-DA-0200B 10/08/86 300.000 038 TV-DA-0200B 11/17/86 0.000 038 TV-DA-0200B 12/10/87 0.269 038 TV-DA-0200B 10/13/88 0.000 038 TV-DA-0200B 09/09/89 0.175 042 2-SA-0081 10/02/86 6.810 042 2-SA-0081 10/27/86 0.000 042 2-SA-0081 10/19/88 0.060 042 2-SA-0082 10/02/86 0.040 042 2-SA-0082 10/27/86 0.000 042 2-SA-0082 10/19/88 0.000 043 2-RM-0003 10/07/86 0.500 043 2-RM-0003 10/27/86 0.020 043 2-RM-0003 09/23/88 0.091 043 TV-RM-0200A 10/07/86 0.110 043 TV-RM-0200A 09/23/88 0.079 044 TV-RM-0200B 10/07/86 0.000 044 TV-RM-0200B 09/23/88 0.000 044 TV-RM-0200C 10/07/86 0.000 044 TV-RM-0200C 09/23/88 0.000 044 TV-RM-0200C 07/06/89 b.000

... _, .. SURRY UNIT 2 CONTAINMENT ISOLATION VALVE TYPE C TEST HISTORY TEST MEASUREMENT PEN NO VALVE NO TEST DATE (SCFH) 045 2-RC-0160 10/15/86 0.610 045 2-RC-0160 09/26/88 0.000 045 TV-RC-2519A 10/15/86 0.000 045 TV-RC-2519A 09/26/88 0.000 045 TV-RC-2519A 07/10/89 0.000 046 FCV-CH-2160 10/10/86 300.000 046 FCV-CH-2160 11/01/86 0.000 046 FCV-CH-2160 09/21/88 16.050 046 FCV-CH-2160 10/03/88 0.000 047 2-IA-0704 10/11 /86 0.000 047 2-IA-0704 10/20/86 0.333 047 2-IA-0704 10/02/88 0.067 047 2-IA-0864 10/11 /86 0.000 047 2-IA-0864 10/02/88 0.000 047 TV-IA-0200 10/11 /86 3.000 047 TV-IA-0200 10/20/86 0.333 047 TV-IA-0200 10/02/88 0.000 048 TV-VG-0209A 10/08/86 0.000 048 TV-VG-0209A 09/27/88 0.000 048 TV-VG-0209A 03/31 /89 0.000 048 TV-VG-02098 10/08/86 0.000 048 TV-VG-02098 09/27/88 0.000 048 TV-VG-02098 04/04/89 0.000 050 TV-Sl-0201 A 11/15/86 2.680 050 TV-Sl-0201 A 11/16/86 0.195 050 TV-Sl-0201 A 11/02/88 0.740 050 TV-Sl-0201 A 12/05/88 0.000 050 TV-Sl-0201 B 10/15/86 0.150 050 TV-Sl-0201 B 11/02/88 0.600 050 TV-Sl-0201 B 12/10/88 0.000

"'*:!' SURRY UNIT 2 CONTAINMENT ISOLATION VALVE TYPE C TEST HISTORY TEST MEASUREMENT PEN NO VALVE NO TEST DATE (SCFH) 051 2-SW-0206 10/05/86 2.420 051 2-SW-0206 11/17/86 0.000 051 2-SW-0206 09/18/88 0.056 051 2-SW-0208 10/05/86 0.000 051 2-SW-0208 11/17/86 0.000 051 2-SW-0208 09/18/88 0.030 / 053 2-Sl-0304 10/09/86 0.910 053 2-Sl-0304 10/27/86 0.390 053 2-Sl-0304 09/19/88 1.500 053 2-Sl-0304 09/24/88 0.000 053 TV-Sl-0200 10/09/86 0.000 053 TV-Sl-0200 09/19/88 1.800 053 TV-Sl-0200 09/24/88 0.275 053 TV-Sl-0200 10/29/88 0.000 054 2-VA-0001 10/11 /86 0.000 054 2-VA-0001 09/26/88 0.000 054 2-VA-0009 10/11 /86 0.000 054 2-VA-0009 09/26/88 0.060 055D TV-LM-0200E 10/05/86 0.000 055D TV-LM-0200E 09/18/88 0.000 055D TV-LM-0200F 10/05/86 0.000 055D TV-LM-0200F 09/18/88 0.000 056A TV-SS-0206A 10/15/86 0.035 056A TV-SS-0206A 09/30/88 0.000 056A TV-SS-0206B 10/15/86 0.035 056A TV-SS-0206B 09/30/88 0.000 SURRY UNIT 2 CONTAINMENT ISOLATION VALVE TYPE C TEST HISTORY TEST MEASUREMENT PEN NO VALVE NO TEST DATE (SCFH) 0568 TV-SS-0202A 10/15/86 0.000 0568 TV-SS-0202A 09/30/88 0.180 0568 TV-SS-0202A 02/14/89 0.000 0568 TV-SS-02028 10/15/86 0.000 0568 TV-SS-02028 09/30/88 2.100 0568 TV-SS-02028 02/14/89 0.025 056D TV-SS-0200A 10/09/86 0.000 056D TV-SS-0200A 11/09/86 0.000 056D TV-SS-0200A 12/09/87 0.150 056D TV-SS-0200A 09/20/88 0.000 056D TV-SS-02008 10/09/86 0.000 056D TV-SS-02008 12/09/87 0.000 056D TV-SS-02008 12/18/87 0.000 056D TV-SS-02008 09/20/88 0.000 056D TV-SS-02008 04/05/90 0.000 057A TV-SS-0201 A 10/09/86 0.060 057A TV-SS-0201 A 11/09/86 0.200 057A TV-SS-0201 A 11/10/86 0.000 057A TV-SS-0201 A 09/30/88 2.500 057A TV-SS-0201 A 07/14/89 1.860 057A TV-SS-0201 A 08/05/89 0.000 057A TV-SS-02018 10/09/86 0.000 057A TV-SS-02018 09/30/88 2.500 057A TV-SS-02018 07/14/89 0.000 0578 TV-DA-0203A 10/07/86 0.000 0578 TV-DA-0203A 10/09/86 0.000 0578 TV-DA-0203A 09/26/88 0.000

,, .. ,,* SURRY UNIT 2 CONTAINMENT ISOLATION VALVE TYPE C TEST HISTORY TEST MEASUREMENT PEN NO VALVE NO TEST DATE (SCFH) 0578 TV-DA-02038 10/07/86 1.200 0578 TV-DA-02038 10/09/86 0.000 0578 TV-DA-02038 09/26/88 0.570 0578 TV-DA-02038 10/29/88 0.000 057C TV-LM-0200G 10/05/86 0.000 057C TV-LM-0200G 09/18/88 0.000 057C TV-LM-0200H 10/05/86 0.000 057C TV-LM-0200H 09/18/88 0.000 057D TV-SS-0204A 10/09/86 0.000 057D TV-SS-0204A 11/09/86 0.000 057D TV-SS-0204A 09/19/88 0.000 057D TV-SS-0204A 09/01/89 0.000 057D TV-SS-02048 10/09/86 0.000 057D TV-SS-02048 09/19/88 0.100 058 1-IA-0704 10/11 /86 0.340 058 1-IA-0704 11/07/86 0.000 058 1-IA-0704 10/02/88 0.410 058 1-IA-0704 11/10/88 0.000 058 2-IA-0868 10/11 /86 3.400 058 2-IA-0868 10/02/88 0.000 058 2-IA-0868 11/10/88 0.280 058 2-IA-0868 07/06/89 0.000 060 MOV-S1-2890A 10/05/86 4.600 060 MOV-S l-2890A 11/15/86 4.130 060 MOV-S1-2890A 09/11 /88 3.050 060 MOV-S1-2890A 09/04/89 0.693

' . SURRY UNIT 2 CONTAINMENT ISOLATION VALVE TYPE C TEST HISTORY TEST MEASUREMENT PEN NO VALVE NO TEST DATE (SCFH) 061 MOV-S1-2890C 10/05/86 2.600 061 MOV-S1-2890C 11/15/86 1.510 061 MOV-S1-2890C 09/12/88 0.000 061 MOV-S l-2890C 09/06/89 0.690 062 MOV-Sl-2890B 10/05/86 0.300 062 MOV-Sl-2890B 11/15/86 2.100 062 MOV-Sl-2890B 09/12/88 4.550 062 MOV-Sl-2890B 09/04/89 0.750 063 2-CS-0024 10/15/86 294.000 063 2-CS-0024 10/30/86 0.000 063 2-CS-0024 09/21/88 180.000 063 2-CS-0024 10/11 /88 0.050 063 2-CS-0024 07/12/89 0.000 063 MOV-CS-0201 C 10/15/86 0.000 063 MOV-CS-0201 C 10/30/86 0.680 063 MOV-CS-0201 C 09/21 /88 0.506 063 MOV-CS-0201 C 07/20/89 0.320 063 MOV-CS-0201 D 10/15/86 0.000 063 MOV-CS-0201 D 10/30/86 0.680 063 MOV-CS-0201 D 09/21/88 0.506 063 MOV-CS-0201 D 07/20/89 0.320 064 2-CS-0013 10/15/86 0.200 064 2-CS-0013 09/21 /88 0.010 064 2-CS-0013 07/12/89 0.000 064 MOV-CS-0201 A 10/15/86 1.200 064 MOV-CS-0201 A 11/11 /86 0.000 064 MOV-CS-0201 A 09/22/88 0.226 064 MOV-CS-0201 A 07/21 /89 0.900 064 MOV-CS-0201 B 10/15/86 1.200 064 MOV-CS-0201 B 11 /11 /86 0.000 064 MOV-CS-0201 B 09/22/88 0.226 064 MOV-CS-0201 B 07/21 /89 0.900 SURRY UNIT 2 CONTAINMENT ISOLATION VALVE TYPE C TEST HISTORY TEST MEASUREMENT PEN NO VALVE NO TEST DATE (SCFH) 066 MOV-RS-0255A 10/14/86 1.850 066 MOV-RS-0255A 11/05/86 1.750 066 MOV-RS-0255A 09/24/88 0.134 066 MOV-RS-0255A 07/14/89 0.526 067 MOV-RS-0255B 10/14/86 1.850 067 MOV-RS-0255B 11/05/86 1.750 067 MOV-RS-0255B 09/24/88 0.134 067 MOV-RS-02558 07/14/89 0.526 068 MOV-S l-2860A 10/14/86 4.300 068 MOV-S l-2860A 11/12/86 1.510 068 MOV-S l-2860A 10/15/88 0.005 068 MOV-S l-2860A 08/20/89 1.000 069 MOV-Sl-2860B 10/14/86 4.300 069 MOV-Sl-2860B 11/12/86 1.510 069 MOV-Sl-2860B 10/15/88 0.005 069 MOV-Sl-2860B 08/20/89 1.000 070 2-RS-0011 10/13/86 1.600 070 2-RS-0011 09/20/88 9.930 070 2-RS-0011 11/30/88 0.330 070 MOV-RS-02568 10/13/86 2.500 070 MOV-RS-02568 11/24/86 3.700 070 MOV-RS-02568 09/02/88 0.000 070 MOV-RS-02568 12/08/88 0.000 070 MOV-RS-02568 07/17/89 0.000 070 MOV-RS-0256 B 09/03/89 0.693 071 2-RS-0017 10/13/86 0.075 071 2-RS-0017 11/16/86 0.600 071 2-RS-0017 05/30/88 0.100 071 2-RS-0017 09/21 /88 0.000 071 2-RS-0017 11/30/88 3.190 071 2-RS-0017 01/18/89 0.000

.. SURRY UNIT 2 CONTAINMENT ISOLATION VALVE TYPE C TEST HISTORY TEST MEASUREMENT PEN NO VALVE NO TEST DATE (SCFH) 071 MOV-RS-0256A 10/13/86 89.000 071 MOV-RS-0256A 11/16/86 6.900 071 MOV-RS-0256A 09/21/88 8.316 071 MOV-RS-0256A 01 /18/89 0.000 071 MOV-RS-0256A 07/24/89 0.000 089 2-VP-0012 10/13/86 8.670 089 2-VP-0012 11/17/86 1.300 089 2-VP-0012 09/27/88 6.600 089 2-VP-0012 10/07/88 0.740 089 TV-SV-0202A 10/13/86 0.850 089 TV-SV-0202A 09/27/88 1.060 089 TV-SV-0202A 10/31 /88 0.000 090 MOV-VS-0200C 10/05/86 4.300 090 MOV-VS-0200C 11/16/86 3.100 090 MOV-VS-0200C 09/11 /88 5.770 090 MOV-VS-0200C 09/04/89 7.700 090 MOV-VS-0200C 10/24/89 11.130 090 MOV-VS-0200C 11/18/89 47.700 090 MOV-VS-0200C 11/19/89 1.500 090 MOV-VS-02000 10/05/86 4.300 090 MOV-VS-02000 11/16/86 3.100 090 MOV-VS-02000 09/11 /88 5.770 090 MOV-VS-02000 09/04/89 7.700 090 MOV-VS-02000 10/24/89 11.130 090 MOV-VS-02000 11/18/89 47.700 090 MOV-VS-02000 11/19/89 1.500 090 MOV-VS-0201 10/05/86 4.300 090 MOV-VS-0201 11/16/86 3.100 090 MOV-VS-0201 09/11 /88 5.770 090 MOV-VS-0201 09/04/89 7.700 090 MOV-VS-0201 10/24/89 11.130 090 MOV-VS-0201 11/18/89 47.700 090 MOV-VS-0201 11/19/89 1.500

-~~-I '-e e .. ' " .. SURRY UNIT 2 CONTAINMENT ISOLATION VALVE TYPE C TEST HISTORY TEST MEASUREMENT PEN NO VALVE NO TEST DATE (SCFH) 091 MOV-VS-0200A 10/05/86 2.500 091 MOV-VS-0200A 11/16/86 4.100 091 MOV-VS-0200A 12/19/87 9.522 091 MOV-VS-0200A 06/17/88 9.270 091 MOV-VS-0200A 09/11 /88 8.500 091 MOV-VS-0200A 09/04/89 1.060 091 MOV-VS-0200A 10/18/89 305.000 091 MOV-VS-0200A 10/24/89 0.000 091 MOV-VS-0200A 11/18/89 272.000 091 MOV-VS-0200A 11 /19/89 4.455 091 MOV-VS-02008 10/05/86 2.500 091 MOV-VS-02008 11/16/86 4.100 091 MOV-VS-02008 12/19/87 9.522 091 MOV-VS-02008 06/17/88 9.270 091 MOV-VS-02008 09/11 /88 8.500 091 MOV-VS-0200B 09/04/89 1.060 091 MOV-VS-02008 10/18/89 305.000 091 MOV-VS-0200B 10/24/89 0.000 091 MOV-VS-02008 11/18/89 272.000 091 MOV-VS-02008 11/19/89 4.455 091 MOV-VS-0202 10/05/86 2.500 091 MOV-VS-0202 11/16/86 4.100 091 MOV-VS-0202 12/19/87 9.522 091 MOV-VS-0202 06/17/88 9.270 091 MOV-VS-0202 09/11 /88 8.500 091 MOV-VS-0202 09/04/89 1.060 091 MOV-VS-0202 10/18/89 305.000 091 MOV-VS-0202 10/24/89 0.000 091 MOV-VS-0202 11/18/89 272.000 091 MOV-VS-0202 11/19/89 4.455 092 TV-CV-0250C 10/10/86 0.600 092 TV-CV-0250C 09/22/88 0.814 092 TV-CV-0250C 11/03/88 0.000

.. e ' " ... SURRY UNIT 2 CONTAINMENT ISOLATION VALVE TYPE C TEST HISTORY TEST MEASUREMENT PEN NO VALVE NO TEST DATE (SCFH) 092 TV-CV-0250D 10/10/86 0.220 092 TV-CV-0250D 09/22/88 0.092 092 TV-CV-0250D 11/03/88 0.000 092 TV-CV-0250D 04/02/90 1.741 092 TV-CV-0250D 04/03/90 2.182 092 TV-GW-0204 10/10/86 0.030 092 TV-GW-0204 09/22/88 0.000 092 TV-GW-0204 01/30/89 0.000 092 TV-GW-0205 10/10/86 0.000 092 TV-GW-0205 09/22/88 0.000 093 TV-CV-0250A 10/10/86 0.000 093 TV-CV-0250A 09/18/88 0.400 093 TV-CV-0250A 11/03/88 0.270 093 TV-CV-02508 10/10/86 0.200 093 TV-CV-02508 09/18/88 0.450 093 TV-CV-02508 10/26/89 0.070 093 TV-GW-0200 10/10/86 0.000 093 TV-GW-0200 09/18/88 0.000 093 TV-GW-0201 10/10/86 0.000 093 TV-GW-0201 09/18/88 0.000 094 2-CV-0002 10/17/86 3.200 094 2-CV-0002 11/03/86 2.500 094 2-CV-0002 09/23/88 0.950 094 HCV-CV-0200 10/17/86 0.550 094 HCV-CV-0200 09/23/88 0.581

" ,, ' .. ,,, . ' V SURRY UNIT 2 CONTAINMENT ISOLATION VALVE TYPE C TEST HISTORY TEST MEASUREMENT PEN NO VALVE NO TEST DATE (SCFH) 0978 TV-SS-0203A 10/12/86 0.000 0978 TV-SS-0203A 09/28/88 0.000 0978 TV-SS-02038 10/12/86 0.000 0978 TV-SS-02038 09/28/88 0.000 097C TV-LM-0200A 10/05/86 0.000 097C TV-LM-0200A 09/18/88 0.000 097C TV-LM-02008 10/05/86 0.000 097C TV-LM-02008 09/18/88 0.000 100 TV-GW-0206 10/10/86 0.000 100 TV-GW-0206 09/30/88 0.000 100 TV-GW-0207 10/10/86 0.000 100 TV-GW-0207 09/30/88 0.000 101 2-FP-0151 10/15/86 0.000 101 2-FP-0151 09/29/88 0.000 101 2-FP-0152 10/15/86 0.000 101 2-FP-0152 09/29/88 0.000 103 2-RL-0003 10/09/86 0.000 103 2-RL-0003 09/22/88 0.000 103 2-RL-0003 01/20/89 0.000 103 2-RL-0005 10/08/86 0.000 103 2-RL-0005 09/22/88 0.000 103 2-RL-0005 01/20/89 0.000

,. e ,, ' ... {,; I. * .. fl SURRY UNIT 2 CONTAINMENT ISOLATION VALVE TYPE C TEST HISTORY TEST MEASUREMENT PEN NO VALVE NO TEST DATE (SCFH) 104 2-RL-0013 10/08/86 0.270 104 2-RL-0013 09/22/88 0.000 104 2-RL-0013 01/20/89 0.000 104 2-RL-0015 10/08/86 0.000 104 2-RL-0015 09/22/88 0.000 104 2-RL-0015 01/20/89 0.000 1058 TV-LM-0200C 10/05/86 0.000 1058 TV-LM-0200C 09/18/88 0.000 1058 TV-LM-02000 10/05/86 0.000 1058 TV-LM-02000 09/18/88 0.000 105C TV-GW-0211A 10/11 /86 0.000 105C TV-GW-0211 A 09/30/88 0.000 105C TV-GW-02118 10/11/86 0.000 105C TV-GW-02118 09/30/88 0.000 106 2-Sl-0073 11/07/86 0.000 106 2-Sl-0073 09/18/88 0.000 112 TV-IA-0201 A 10/11/86 0.042 112 TV-IA-0201 A 09/30/88 0.000 112 TV-IA-02018 10/11 /86 0.843 112 TV-IA-02018 09/30/88 0.220 113 2-Sl-0174 10/05/86 0.000 113 2-Sl-0174 11/15/86 0.000 113 2-Sl-0174 09/11 /88 0.095 113 2-Sl-0174 07/27/89 0.261

.... J I " .. ,.,, ., .. '""* . .,, PEN NO 113 113 113 113 e SURRY UNIT 2 CONTAINMENT ISOLATION VALVE TYPE C TEST HISTORY VALVE NO MOV-S1-2869A MOV-S1-2869A MOV-S1-2869A MOV-S1-2869A TEST DATE 10/05/86 11/15/86 09/11 /88 07/27/89 TEST MEASUREMENT (SCFH) 0.000 0.000 0.095 0.261