IR 05000280/1985020
| ML18143B323 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 06/27/1985 |
| From: | Jape F, Macdonald J, Mellen L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18143B322 | List: |
| References | |
| 50-280-85-20, 50-281-85-20, NUDOCS 8508020158 | |
| Download: ML18143B323 (12) | |
Text
Report Nos.:
50-280/85-20 and 50-281/85-20 Licensee:
Virginia Electric and Power Company Richmond, VA 23261 Docket Nos.:
50-280 and 50-281 License Nos.:
DPR-32 and DPR-37 Facility Name:
Surry 1 and 2 Inspection Conducted:
May 31 - June 10, 1985 Inspectors: cf.~?~
L. S. Mellen U.§, ??(JzdA1<a/lL
~: Macdo~a
.
Approved by:
Ce,,:,(,~ ~
Frank Jape~tion Cle Engineering Branch Division of Reactor Safety SUMMARY 6 /17/8:;-
Date Signed
~z/es-tfie Signed eoif7Ll>
Dae Signed Scope:
This routine, unannounced inspection entailed 230 inspector-hours on site in the areas of procedure review and witnessing the 10 CFR 50 Appendix J Type A, B, and C leak rate testin Results:
No violations or deviations were identified *
--
50702
,.,------9500020001 ~~ isooo200
PDR A
PDR G
REPORT DETAILS Persons Contacted Licensee Employees
- H. L. Miller, Assistant Station Manager (NS&L)
- D. L. Benson, Assistant Station Manager (O&M)
- R. H. Blount, Supervisor Performance and Technical R. Allen, Reactor Operator E. J. Turko, Engineer Other licensee employees contacted included construction craftsmen, engineers, technicians, operators, mechanics, and office personne Other Organizations Stone and Webster
- R. I. Samson, Engineer NRC Resident Inspectors
- D. Burke, Senior Resident Inspector
- M. Davis, Resident Inspector
- Attended exit interview Exit Interview The inspection scope and findings were summarized on June 10, 1985, with those persons indicated in paragraph 1 abov The inspector described the areas inspected and discussed in detail the inspection finding No dissenting comments were received from the license The following inspector followup items were identified: IFI (280/85-20-01) Revision of Technical Specification to permit an imposed leakage verification test for Appendix J, Type A testin IFI (280/85-20-02) Improvement in data acquisition and data/time correlation for ILR The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspectors during this inspectio.
Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspectio *
2 Unresolved Items Unresolved items were not identified during the inspectio.
Type A Test Sequence and Description (61719)(90713)
Pressurization of containment was started at 0145 hours0.00168 days <br />0.0403 hours <br />2.397487e-4 weeks <br />5.51725e-5 months <br /> on June 7, 198 After resolving containment air recirc fan problems, a containment pressure of 61.557 psia was achieved at 1338 hour0.0155 days <br />0.372 hours <br />0.00221 weeks <br />5.09109e-4 months <br /> Containment stabilization criterion was met at 1750 hour0.0203 days <br />0.486 hours <br />0.00289 weeks <br />6.65875e-4 months <br /> During pressurization, stabilization and the next seven hours an extensive leakage investigation revealed only minor seat or packing leakage on the following valves:
MOV-2289A TV-SI-200B TV-VA-203A 2-DG-l 2-RM-6 2-RM-12 2-IA-977 2-IA-992 2-SI-212 I-IA-702 I-IA-703 I-IA-704 (Penetration X-15)
(Penetration X-53)
(Penetration X-57B)
(Penetration X-33)
(Penetration X-43)
(Penetration X-44)
(Penetration X-47)
(Penetration X-47)
(Penetration X-53)
(Penetration X-58)
(Penetration X-58)
(Penetration X-58)
Pressurization checks on the Mainsteam lines revealed:
A 5.9 psig B
O psig C
O psig At 2235 hours0.0259 days <br />0.621 hours <br />0.0037 weeks <br />8.504175e-4 months <br />, the walkdown of electrical penetration area indicated penetration 3C increasing in pressure to approximately 31 psi However, there was no measurable through penetration leakag At 2310 hours0.0267 days <br />0.642 hours <br />0.00382 weeks <br />8.78955e-4 months <br />, reading The previous ILR future ILRT chilled mirror #10 was removed from service due to erratic inspector noted this chilled mirror had failed during the The licensee indicated this mirror would not be used during At 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> on June 8, 1985, having performed an extensive leakage evaluation, the licensee met the containment stabilization criteria as established in BN-TOP-1 1972 Revision 1, Section 2.3. The rate of change of average temperature was less than l.0°F/hour when averaged between 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on June 7 and 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> on June 8.
r
At 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br /> on June 8, the ILRT met all criteria established in 8N-TOP-1 Section 2.3.8, for test termination as noted below:
Criteria The trend report based on total time calculations was less than maximum leakage rate allowable (Note:
8N-TOP-1 Section 2.3.8.1, indicates the maximum allowable leakage is L However, 10 CFR 50 Appendix J, which was issued subsequent to 8N-TOP-1, reduces this to 0.75L In cases where there is conflict between test methods and the regulations, the regulations govern).
Criteria The end of test upper confidence limit for the calculated leak rate based on total time was less than 0.75La (note discussion in Criteria 8.1) including the as-found leakage and the type 8 and C leakage penaltie Criteria The mean of the measured leak rates based on total time calculations over the last points was below 0.75La (note discussions in Criteria 8.1).
Criteria Data was recorded at equal 20 minute intervals (note discussion on data acquisition Section 9).
Criteria The 13.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> test provided more than the minimum (20) data sets required by 8N-TOP-Criteria The test duration of 13.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> exceeded the minimum require-ments of 8N-TOP-Criteria At 1835 hours0.0212 days <br />0.51 hours <br />0.00303 weeks <br />6.982175e-4 months <br />, stabilization for the superimposed verifica-tion test was complete The stabilization period of four hours exceeded the one hour requirement of 8N-TOP-Criteria The verification test duration was 9.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, was concluded at 0530 hours0.00613 days <br />0.147 hours <br />8.763227e-4 weeks <br />2.01665e-4 months <br /> on June 9, 1985, and exceeded the minimum required duration of 6.75 hour8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> Criteria The resulting measured verification leakage agreed within 25%
of the calculated leakag Time Hours Date 0145 1338 (6/8)
( 6/8)
SYNOPSIS OF UNIT TWO TYPE A TEST JUNE 8 - 10, 1985 Containment pressurization began Pressurization was secured
i
- (6/8)
Started containment stabilization 2310 ( 6/8)
Removed chilled mirror #10 from service 0100 (6/9)
ILRT began 1430 (6/9)
Ended ILRT 1646 (6/9)
Began verification test stabilization 1835 (6/9)
Superimposed verification stabilization completed, verification began 0530 ( 6/10)
Superimposed verification completed 0830 (6/10)
Depressurization began Supplemental Test Technical Specification During discussions of acceptable methods for performing the supplemental test, the licensee pointed out that Technical Specification 4.4 states that the makeup air method will be used for the supplemental test. The Technical Specification further states that the leak rate test will be performed in accordance with Appendix J to 10 CFR 50 which recommends that the imposed leak rate method specified in ANSI N45.4 be used for the supplemental tes In a case where regulations conflict with Technical Specifications the regulations, being a higher level document, will govern unless the Technical Specification is identified as an exemption to the regulatio The inspectors concluded that the licensee's Technical Specification will permit the use of the imposed leak rate method for performing the supplemental tes The licensee indicated that this ambiguity will be clarified in a future Technical Specification submitta This was identified as Inspector Followup Item IFI (280/85-20-01). As-Found Leak Rate (61719)
A preliminary analysis of the as-found type A leakage rate was provided to the inspector The results are summarized below:
Penetration N Safety Injection 21 Safety Injection 28 Chemical & Vol. Control 33 Gaseous Drains 38 Aerated Drains 43 Air Monitoring Inside 22 '10.655 1.947 Outside 6.2 1.39 _ 18.0 Net Leakage SCFH 0.39.655 *
46 Charging 1.05 Instrument Air 12.203.0 50 Safety Injection 0.435 0.435 53 Safety Injection.6584 A Liquid Sample 3.323 2.7926 2.7926 568 Liquid Sample 0.131 0.238 0.131 560 Liquid Sample.088 1.088 57A Leakage Mo.74 4.47 0.74 570 Sample System.76 Instrument Air 0.966.0 63 Cont. Spray.52 Cont. Spray.3 Recirc. Spray.21 Air Ejec. Dsc.29.0 90 Ventilation.139 Ventilation.3 Cont. Vacuum 1.21 1.21 93 Cont. Vacuum 4.92 4.92 101 Fire Pra.0 113 Safety Injection 1.52 Penetrations not listed had zero leakag The as-found local leakage rate test results indictaed a total leakage of 33.6 SCFH or 0.011 wt%/da The pathways that were identified in the September 1983, test as having leakage of greater th-an 40 SCFH had measured leakage below 40 SCFH during this test. The results were as follows:
Penetration N Aerated Drums 46 Charging 69 Recirculation Spray Net Leakage SCFH 20.655.0 Based on the preliminary analysis discussed above, the inspectors concluded that the licensee had demonstrated that the as-found containment leakage meets the Appendix J leakage of 0.075 wt%/da The licensee has adequately addressed the as found leakage from type Band C tests. This closes !FI 281/83-27-01 *
6 As Left Leak Rate (61720)
The preliminary analysis of As-Left local leak rate data indicated the as-left leakage was less than 31 SCF This was well below the limit of 0.6L The individual valve and penetration data is tabularized below:
Leak Rate Penetration Leakage Penetration N Valve N {SCFH}
(SCFD}
2-SI-150 (A)
MOV-2867 C&D.2
2-CH-309 0.29 MOV-2289A 0.307 7.368
MOV-2381
0
2-SI-32
0
MOV-2842
0
MOV-28698 0.24 5.76
MOV-RH-200
0
HCV-2200A,B,C 0.72 TV-2204.0
TV-GW-203
TV-GW-202
0
TV-DG-208A
TV-DG-2088 0.115 2.76
TV-DA-200A 0.145 TV-DA-2008 0.182 4.37
2-SA-81
2-SA-82
0
2-RM-3 0.013 TV-RM-200A 0.068 1.632
TV-RM-2008
TV-RM-200C
0
2-RC-160
TV-2519A
0
FCV-2160 0.25 IA-864 0.027 TV-IA-200 0.0169 2-IA-704
0.648
TV-VG-209A
TV-VG-2098
0
TV-SI-201A 0.085 TV-SI-2018 0.35 SW-206
2-SW-208 0.023 0.55
TV-SI-200 0.0416 2-SI-234 0 VA-1
2-VA-9
0 550 TV-LM-200E (B)
57C TV-LM-200G (B)
97C TV-LM-200A (8)
1058 TV-LM-200C
0 55D TV-LM-200F (C)
57C TV-LM-200H ( C)
97C TV-LM-2008 (C)
1058 TV-LM-200D
0 56A TV-SS-206A 0.027 TV-SS-2068 0.0074 0.648 568 TV-SS-202A 0.034 TV-SS-2028 0.075 D TV-SS-200A
TV-SS-2008 0.112 2.69 57A TV-SS-201A
TV-SS-2018 0.03 o. 72 57B TV-DA-203A
TV-DA-203B
0 57D TV-SS-204A
TV-SS-204B 0.10 LA-868
l-IA-704
0
MOV-2890A.8
MOV-2890C.2
MOV-2890B
0
2-CS-24 MOV-CS-201C,D 0.48 2 CS-13 MOV-CS-201A,8
2,69 MOV-RS-255A&B 0.69 1,67 MOV-2860A&B.0
2-RS-11 MOV-RS-256B 3.78 90. 72
2-RS-17
MOV-RS-256A 1.63 39.12
2-VP-12 0.43 TV-SV-202A
10.32
MOV-VS-200C (D)
MOV-VS-200D&201
.461 11.064
MOV-VS-200A (E)
MOV-VS-2008&202.
TV-CV-250C 0.29 TV-CV-250D 0.29 TV-GW-204
TV-GW-205
6.96
TV-GW-200
TV-GW-201
TV-CV-250A 0.082 TV-CV-2508 0.18 4.32
HCV-CV-200 0.20 2-CV-2 0.083.
978 TV-SS-203A 0.0185 TV-SS-2038 0.0452 1.085 100 TV-GW-206
TV-GW-207
0 101 2-FP-151
2-FP-152
0 103 2-RL-3 ( F)
2-RL-5
0 104 2-RL-13
2-RL-15
0 105C TV-GW-211A
TV-GW-2118
0 106 2-SI-73
0 112 TV-LA-201A
TV-LA-2018
0 113 2-SI-174 &
MOV-2869A 0.58 13. 92 (A)
included with valves MOV-2867 C&D (B)
included with valve TV-LM-200C (C)
included with valve TV-LM-200D ( D)
included with valves MOV-VS-200D & 201 (E)
included with valves MOV-VS-2008 & 202 ( F)
included with valve 2-RL-5 Data Acquisition The process of determining current leakage rate values via corporate computer in Richmond appeared awkwar It involved reading data from a plant process computer, transcribing the data on the logs, hand entering the data on a terminal tied by phone line to the corporate computer in Richmond and waiting for the information to return from the corporate compute During the test, data was completely or partially reentered several times due to Richmond's computer problem There were periods that the leak rate determination was delayed more than an hou In addition, the plant process computer was not printing out the correct times for various data sets this required manual entry of time on log sheet The licensee has agreed to correct the computational problems before the next ILR This was Identified as inspector Followup Item (280/85-20-02):
Improvement in data acquisition and data/time correlation for ILR.
Valve Alignment Verification The inspectors selected a sample population of containment p1p1ng system penetratitin The containment isolation valves of these penetrations were inspected-to ensure that the valves were tagged out and that the valves were in the proper test positio PT 16.3 Reactor Containment Building Inte-grated Leak Rate Test procedure was reviewed to confirm that double independent verification sign-off for valve location and test position was performe In addition, the inspector reviewed the control room tag-out
i
distribution list for motor operated valves and inspected the individual valve controller switches to ensure that each was tagged-out to prevent inadvertent actuation during the test. The penetrations and valves reviewed are identified belo Valve Position Verification PENETRATION 61 - Low Head Safety Injection Disc SI 179 (1)
2 SI 189 (1) * *
MOV 289 OC PENETRATION 63 - Containment Spray Pump Disc cs
MOV-CS-201 C MOV-CS-201 D PENETRATION 64 - Containment Spray Pump Disch 2-CS-63(1) *
MOV-CS-201A MOV-CS-201B PENETRATION 70 - Recircuration Spray ~ump D 2-RS-8 2-RS-25(1) *
2-RS-33(1) *
MOV-RS-256B PENETRATION 71 - Recirc Spray Pump Disc RS-10 2-RS-80(1)
2-RS-81 (1) *
2-RS-85(1) *
MOV-RS-256A PENTRATION 89 - Air Ejector Disch. to Containment 2-VP-186(1)
TV-SV-202A PENETRATION 90 - Containment Purge Exhaust Line 2-VS-225(1)
MOV-VS-200 C (inside cont.)**
MOV-VS-200 D MOV-VS-201
PENETRATION 91 - Ventilation System 2-VS-256(1) *
MOV-VS-200A (inside cont)**
MOV-VS-200B MOV-VS-202 PENETRATION 106 - Safety Injection Test Line 2-SI-73 2-S I-182 (1)
2-SI-184(1)
2-SI-223(1)
HCV-2850A (inside cont) **
HCV-2850B (inside cont) **
HCV-2850C (inside cont) **
HCV-2850D (inside cont) **
HCV-2850E (inside cont) **
HCV-2850F (inside cont) **
(1) indicates nipple was teflon taped and capped
- valves inside containment Of the sample penetrations inspected all valves were found to be tagged-out and in the proper test positio Double independent verification sign-off for valve location and correct test position was complete as per procedure P.T. 1 The sample motor operated valves were identified on the control room tag-out distribution list and each individual controller switch for these valves was properly tagged ou.
Procedure Review PT 16.3 Attachment 7.16 Attachment 7.16, Superimposed Leakage Verification Test, adequately covers the verification criteria for both the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> type A test and the shorter duration test (BN-TOP-1 Rev. 1).
The acceptance criteria described meets or exceeds the requirements of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test and the shorter duration tes The valve alignment and piping configuration appeared adequate to ensure an accurate verification tes The verification test required a minimum number of data sets and test duration to ensure statistical accurac The equations used for calculation of leakage rate were correct and the accuracy of the methodology employed was within the requirements of 10 CFR 50 Appendix The inspectors reviewed Surry Power Procedure ADM-60, in particular Section 5.2, New Procedure Preparation, and Section 5.8.8, Periodic Test Procedures, to check conformance of new procedures PT.16.3 and 2 PT-1 Revised procedures PT-16.3 Reactor Containment -Building Integrated Leak Rate Test (Type 11A
)
and 2-PT-16.4 Containment
. *\\"
Isolation Valve Leakage (Type C testing) were found to be in con-formance with the applicable requirements of the sections of ADM-6 Within the areas examined, no violations or deviations were identified.