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| issue date = 12/13/1983
| issue date = 12/13/1983
| title = Forwards Reactor Containment Bldg Integrated Leak Rate Test-Types A,B & C, Local Leak Rate Test Summary Analysis
| title = Forwards Reactor Containment Bldg Integrated Leak Rate Test-Types A,B & C, Local Leak Rate Test Summary Analysis
| author name = STEWART W L
| author name = Stewart W
| author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
| author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
| addressee name = DENTON H R
| addressee name = Denton H
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000281
| docket = 05000281
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:* ,VIRGINIA ELECTRIC AND POWER COMPANY RICHM.OND,VIRGINIA 23261 December 13, 1983 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn: Distribution Services Branch, DPC, ADM. U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Gentlemen:
{{#Wiki_filter:*
Serial No. 708 NO/WDC:jab Docket No. 50-281 License No. DPR-37 In accordance with 10CFR50, Appendix J, Section V.B., the Virginia Electric and Power Company submits the Reactor Containment Building Integrated Leak Rate Test Type A, B, and C for Surry Power Station Unit No. 2. As requested by the NRC, added as an attachment to this letter is. an analysis of the containment penetrations that were repaired during the 1983 Surry Unit 2 refueling outage. The analysis adds containment penetration "as-found" leakage to the Type A test results to determine the acceptability of the Type A test considering as found leakage. Enclosure cc: Mr. james P. O'Reilly Regional Administrator Region II Mr. D. J. Burke NRC Resident Inspector Surry Power Station 8312200467 831213 PDR ADOCK 05000281 P PDR Very truly yours, ()\_~ W. L. Stewart I *, ' , . , *, \ LOCAL LEAK RATE TEST  
                    ,VIRGINIA ELECTRIC AND POWER COMPANY RICHM.OND,VIRGINIA 23261 December 13, 1983 Mr. Harold R. Denton, Director                           Serial No. 708 Office of Nuclear Reactor Regulation                     NO/WDC:jab Attn: Distribution Services Branch, DPC, ADM.             Docket No. 50-281 U.S. Nuclear Regulatory Commission                       License No. DPR-37 Washington, D.C. 20555 Gentlemen:
In accordance with 10CFR50, Appendix J, Section V.B., the Virginia Electric and Power Company submits the Reactor Containment Building Integrated Leak Rate Test Type A, B, and C for Surry Power Station Unit No. 2.
As requested by the NRC, added as an attachment to this letter is. an analysis of the containment penetrations that were repaired during the 1983 Surry Unit 2 refueling outage. The analysis adds containment penetration "as-found" leakage to the Type A test results to determine the acceptability of the Type A test considering as found leakage.
Very truly yours,
()\_~
W. L. Stewart Enclosure cc: Mr. james P. O'Reilly Regional Administrator Region II Mr. D. J. Burke NRC Resident Inspector Surry Power Station 8312200467 831213 PDR ADOCK 05000281 P                 PDR
 
LOCAL LEAK RATE TEST  


==SUMMARY==
==SUMMARY==
ANALYSIS After the performance of the Type A Test, a request was made by the Nuclear Regulatory Commission to provide an analysis of the containment pentrations that were repaired during ~he 1983 Surry Unit No. 2 Refueling Outage. The details of this ana1ysis are shown on *the following pages. A conservative analysis of the repairs indicates that only _ Pentration 38 would have potentially impacted the "as-found" Type A test results. The local leak rate test for both valves (each was tested individually) indicated a seat leakage in excess of 40 standard cubic feet per hour (scfh). Actual seat leakage could not be recorded, as this represents the highest range flowmeter used for Type C testing at Surry. If the actual seat leakage had been in excess of 124 scfh, the "As-Found" Type A test results would have exceeded the acceptance criteria.
ANALYSIS
In order to prevent this situation from happening again, VEPCO will perfom the following actions: a. Evaluate the test equipment used for local leak rate testing to provide capability for measuring seat leakage up t~ the equivalent of leakage allowed (La) in scfh. b. Initiate an evaluation of Penetration 38 to determine the potential cause for valve degradation in order to develop* a*corrective action program. The results of these evaluations will be reported separately by letter and not as an addendum to this report. Specific penetrations were repaired during the 1983 Surry Unit No.2 refueling outage. The effect of each repair was analyzed to predict the outcome of the Type A test if it were performed prior to the repairs.
*,I
  '      After the performance of the Type A Test, a request was made by the Nuclear Regulatory Commission to provide an analysis of the containment pentrations that were repaired during ~he 1983 Surry Unit No. 2 Refueling Outage. The details of this ana1ysis are shown on *the following pages.
A conservative analysis of the repairs indicates that only
_ Pentration 38 would have potentially impacted the "as-found" Type A test results. The local leak rate test for both valves (each was tested individually) indicated a seat leakage in excess of 40 standard cubic feet per hour (scfh). Actual seat leakage could not be recorded, as this represents the highest range flowmeter used for Type C testing at Surry. If the actual seat leakage had been in excess of 124 scfh, the "As-Found" Type A test results would have exceeded the acceptance criteria.
In order to prevent this situation from happening again, VEPCO will perfom the following actions:
: a. Evaluate the test equipment used for local leak rate testing to provide capability for measuring seat leakage up t~ the equivalent of leakage allowed (La) in scfh.
: b. Initiate an evaluation of Penetration 38 to determine the potential cause for valve degradation in order to develop* a*corrective action program.
The results of these evaluations will be reported separately     by letter and not as an addendum to this report.
Specific penetrations were repaired during the 1983 Surry Unit No.2 refueling outage. The effect of each repair was analyzed to predict the outcome of the Type A test if it were performed prior to the repairs.
* Each :penetration is reviewed using the following criteria;**
* Each :penetration is reviewed using the following criteria;**
: a. A leakage equivalent to the repair is. calculated for each valve in the penetration.
: a. A leakage equivalent to the repair is. calculated for each valve in the penetration.
: b. The leakage equivalent is the difference between the "as-found" and the "as-left" LLRT valves. c. If a repair was not performed, a zero leakage equivalent is assessed to the valve. d. The leakage reduced due penetration.
: b. The leakage equivalent is the difference between the "as-found" and the "as-left" LLRT valves.
be provided.
: c. If a repair was not performed, a zero leakage equivalent is assessed to the valve.
equivalent assessed to a penetration maybe to the safety-related service of the Justification for these penetrations will l of 3
: d. The leakage   equivalent assessed to a penetration maybe reduced due  to the safety-related service of       the penetration. Justification for these penetrations will be provided.
'\ { e .. The net leakage equivalent will be added to the leakage result of Section 3.3.2. f. If the results of the "as-found".Type A are. less than 0.1 percent/day, the test is declared a success. The following penetrations were repaired .. Penetration 7 Safety Injection 28 Chemical and Volume Control 33 Gaseous Drains 38 Aerated Drains 45 Primary Grade Water 46 Charging 47 Instrument Air 50 Safety Injection 56B Sample System 69 Recirculation Spray 92 Containment Vacuum 93 Containment.
      \
Vacuum 94 Containment Vacuum Inside >40 0.5 >40 0.6 1.1 >40 0 0.3 Outside 6.1 0 0 >40 ..-0 >40 1.9 0 1. 6 >40 7 0.8 0.5 Net 6.1 0 0 >40 0 0 1.1 0 0 0 7 0.8 0.3 Remarks See Note 1 -See Note 2 See Note 3 Methods were applied, as described in (e) and (f) above, with the results listed below. 1. Net Equivalent Leakage 2. "As-found" Type A-TT a. b. Total Time Analysis from 3.3.2.1 Net Equivalent Leakage 2 of 3 >55.3 scfh (Percent/Day) 0.060643 >0.018152
l of 3
*. ( C * . e "As-Found" Type A-Total Time Analysis 3. "As-found" Type A-MP a. b. c. CONCLUSION Mass Point Analysis from 3 . 3 . 2 . 2 \ Net Equivalent Leakage "As-found" Type A-Mass Point Analysis >0.078795 (Percent/Day) 0.029158 >0.018152
 
>0.047310 The "as-found" Type A results using the Total Time and the Mass Point Analysis indicate that there is a potential for exceeding the respective limits of 0.1 and 0.75 percent/day.
e .. The net leakage equivalent will be added to the leakage result of Section 3.3.2.
NOTES 1. Greater than 40 scfh represent the largest flowrneter used for the 1983 LLRT program. 2. This line is from the charging pump header and is used to fill the loops. The charging pumps are used as the high head safety injection pumps. The chemical and volume control system valves, piping, and components have been designed to permit essentially zero leakage. Periodic surveillance is performed to verify leakage is within specifications.
'\    f. If the results of the "as-found".Type A are. less than 0.1 percent/day, the test is declared a success.
Reference UFSAR 6.2.3.10 External Recirculation Loop Leakage. 3. The recirculation spray system is designed to operate after the DBA LOCA to depressize the containment to subatmospheric pressure (within approximately 40 minutes).
The following penetrations were repaired ..
The sumps' lines are filled with water and would prevent atmospheric outleakage_either through operation and/or static head. ( 3 of 3 ,,}}
Penetration               Inside    Outside    Net    Remarks 7   Safety Injection                     6.1    6.1 28 Chemical and           >40        0        0 Volume Control 33 Gaseous Drains         0.5        0        0 38 Aerated Drains         >40       >40..-    >40     See Note 1 45  Primary Grade          0.6       0         0 Water 46  Charging                          >40       0    - See Note 2 47  Instrument Air          1.1        1.9       1.1 50  Safety Injection        >40       0        0
{
56B Sample System          0         1. 6     0 69  Recirculation                      >40       0       See Note 3 Spray 92  Containment                        7        7 Vacuum 93  Containment.                      0.8      0.8 Vacuum 94  Containment            0.3        0.5      0.3 Vacuum Methods were applied, as described in (e) and (f) above, with the results listed below.
: 1. Net Equivalent Leakage                   >55.3 scfh
: 2. "As-found" Type A-TT                     (Percent/Day)
: a. Total Time Analysis           0.060643 from 3.3.2.1
: b. Net Equivalent Leakage         >0.018152 2 of 3
 
    *.                 e C * . "As-Found" Type A-Total             >0.078795 Time Analysis
(
: 3. "As-found" Type A-MP                           (Percent/Day)
: a. Mass Point Analysis                 0.029158 from 3 . 3 . 2 . 2 \
: b. Net Equivalent Leakage             >0.018152
: c.    "As-found" Type A-Mass             >0.047310 Point Analysis CONCLUSION The "as-found" Type A results using the Total Time and the Mass Point Analysis indicate that there is a potential for exceeding the respective limits of 0.1 and 0.75 percent/day.
NOTES
: 1. Greater than 40 scfh represent the largest flowrneter used for the 1983 LLRT program.
: 2. This line is from the charging pump header and is used to fill the loops. The charging pumps are used as the high head safety injection pumps.           The chemical and volume control system valves, piping, and components have been designed to permit essentially zero leakage. Periodic surveillance is performed to verify leakage is               within   specifications.
Reference UFSAR 6.2.3.10 External Recirculation Loop Leakage.
: 3. The recirculation spray system is designed to operate after the DBA LOCA to depressize the containment to subatmospheric pressure (within approximately 40 minutes). The sumps' lines are filled with water and               would   prevent   atmospheric outleakage_either through operation and/or static head.
(                                           3 of 3
,,}}

Latest revision as of 00:48, 3 February 2020

Forwards Reactor Containment Bldg Integrated Leak Rate Test-Types A,B & C, Local Leak Rate Test Summary Analysis
ML18141A272
Person / Time
Site: Surry Dominion icon.png
Issue date: 12/13/1983
From: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To: Harold Denton
Office of Nuclear Reactor Regulation
Shared Package
ML18141A273 List:
References
708, NUDOCS 8312200467
Download: ML18141A272 (4)


Text

,VIRGINIA ELECTRIC AND POWER COMPANY RICHM.OND,VIRGINIA 23261 December 13, 1983 Mr. Harold R. Denton, Director Serial No. 708 Office of Nuclear Reactor Regulation NO/WDC:jab Attn: Distribution Services Branch, DPC, ADM. Docket No. 50-281 U.S. Nuclear Regulatory Commission License No. DPR-37 Washington, D.C. 20555 Gentlemen:

In accordance with 10CFR50, Appendix J, Section V.B., the Virginia Electric and Power Company submits the Reactor Containment Building Integrated Leak Rate Test Type A, B, and C for Surry Power Station Unit No. 2.

As requested by the NRC, added as an attachment to this letter is. an analysis of the containment penetrations that were repaired during the 1983 Surry Unit 2 refueling outage. The analysis adds containment penetration "as-found" leakage to the Type A test results to determine the acceptability of the Type A test considering as found leakage.

Very truly yours,

()\_~

W. L. Stewart Enclosure cc: Mr. james P. O'Reilly Regional Administrator Region II Mr. D. J. Burke NRC Resident Inspector Surry Power Station 8312200467 831213 PDR ADOCK 05000281 P PDR

LOCAL LEAK RATE TEST

SUMMARY

ANALYSIS

  • ,I

' After the performance of the Type A Test, a request was made by the Nuclear Regulatory Commission to provide an analysis of the containment pentrations that were repaired during ~he 1983 Surry Unit No. 2 Refueling Outage. The details of this ana1ysis are shown on *the following pages.

A conservative analysis of the repairs indicates that only

_ Pentration 38 would have potentially impacted the "as-found" Type A test results. The local leak rate test for both valves (each was tested individually) indicated a seat leakage in excess of 40 standard cubic feet per hour (scfh). Actual seat leakage could not be recorded, as this represents the highest range flowmeter used for Type C testing at Surry. If the actual seat leakage had been in excess of 124 scfh, the "As-Found" Type A test results would have exceeded the acceptance criteria.

In order to prevent this situation from happening again, VEPCO will perfom the following actions:

a. Evaluate the test equipment used for local leak rate testing to provide capability for measuring seat leakage up t~ the equivalent of leakage allowed (La) in scfh.
b. Initiate an evaluation of Penetration 38 to determine the potential cause for valve degradation in order to develop* a*corrective action program.

The results of these evaluations will be reported separately by letter and not as an addendum to this report.

Specific penetrations were repaired during the 1983 Surry Unit No.2 refueling outage. The effect of each repair was analyzed to predict the outcome of the Type A test if it were performed prior to the repairs.

  • Each :penetration is reviewed using the following criteria;**
a. A leakage equivalent to the repair is. calculated for each valve in the penetration.
b. The leakage equivalent is the difference between the "as-found" and the "as-left" LLRT valves.
c. If a repair was not performed, a zero leakage equivalent is assessed to the valve.
d. The leakage equivalent assessed to a penetration maybe reduced due to the safety-related service of the penetration. Justification for these penetrations will be provided.

\

l of 3

e .. The net leakage equivalent will be added to the leakage result of Section 3.3.2.

'\ f. If the results of the "as-found".Type A are. less than 0.1 percent/day, the test is declared a success.

The following penetrations were repaired ..

Penetration Inside Outside Net Remarks 7 Safety Injection 6.1 6.1 28 Chemical and >40 0 0 Volume Control 33 Gaseous Drains 0.5 0 0 38 Aerated Drains >40 >40..- >40 See Note 1 45 Primary Grade 0.6 0 0 Water 46 Charging >40 0 - See Note 2 47 Instrument Air 1.1 1.9 1.1 50 Safety Injection >40 0 0

{

56B Sample System 0 1. 6 0 69 Recirculation >40 0 See Note 3 Spray 92 Containment 7 7 Vacuum 93 Containment. 0.8 0.8 Vacuum 94 Containment 0.3 0.5 0.3 Vacuum Methods were applied, as described in (e) and (f) above, with the results listed below.

1. Net Equivalent Leakage >55.3 scfh
2. "As-found" Type A-TT (Percent/Day)
a. Total Time Analysis 0.060643 from 3.3.2.1
b. Net Equivalent Leakage >0.018152 2 of 3
  • . e C * . "As-Found" Type A-Total >0.078795 Time Analysis

(

3. "As-found" Type A-MP (Percent/Day)
a. Mass Point Analysis 0.029158 from 3 . 3 . 2 . 2 \
b. Net Equivalent Leakage >0.018152
c. "As-found" Type A-Mass >0.047310 Point Analysis CONCLUSION The "as-found" Type A results using the Total Time and the Mass Point Analysis indicate that there is a potential for exceeding the respective limits of 0.1 and 0.75 percent/day.

NOTES

1. Greater than 40 scfh represent the largest flowrneter used for the 1983 LLRT program.
2. This line is from the charging pump header and is used to fill the loops. The charging pumps are used as the high head safety injection pumps. The chemical and volume control system valves, piping, and components have been designed to permit essentially zero leakage. Periodic surveillance is performed to verify leakage is within specifications.

Reference UFSAR 6.2.3.10 External Recirculation Loop Leakage.

3. The recirculation spray system is designed to operate after the DBA LOCA to depressize the containment to subatmospheric pressure (within approximately 40 minutes). The sumps' lines are filled with water and would prevent atmospheric outleakage_either through operation and/or static head.

( 3 of 3

,,