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See also: [[see also::IR 05000281/1986036]]


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{{#Wiki_filter:VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIBGINIA 23261 W. L. STBWABT VxcB PREBIDE>l'T  
{{#Wiki_filter:VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIBGINIA 23261 W. L. STBWABT VxcB PREBIDE>l'T NUCLBAB 0PEBAT10"8
NUCLBAB 0PEBAT10"8  
* October 8, 1987 U. s. Nuclear Regulatory O'mni ssim Attn: I)*x:nment cart:rol Desk Washirgtm, D.C.
* October 8, 1987 U. s. Nuclear Regulatory  
* 20555 Gentlemen:
O'mni ssim Attn: I)*x:nment  
VIRID{IA ET& :IRLC AND R'.JrlER SCllm RNm smTiaf tmTS 1 AND 2 . NRC INSPECl'Iaf REEtRl! R>. 50-28U86-36 Serial.No.
cart:rol Desk Washirgtm, D.C. * 20555 Gentlemen:  
NO/En'S :vlh Dx:ket Nos. License Nos. 87-570 R3 50-280 50-281 m:R-32 DPR-37 We have reviewed ya.ir letter of Septeni:>er 8, 1987, in refererx:e to the Notice of Violation is.sued with Inspection Report 50-281/86-36 an Mardi 2, 1987. additional response to the Notice of Violation is in the attachment.
VIRID{IA ET& :IRLC AND R'.JrlER SCllm RNm smTiaf tmTS 1 AND 2 . NRC INSPECl'Iaf  
We :request that ya.ir :reevaluatim of this violation be postponed, perrlin;J resolution of the tedmical issue by NRR. '!he basis for our :request is provided in the attadmlent.
REEtRl! R>. 50-28U86-36  
If you have arr:/ further questions, please contact. us. Very truly yoors, W. L. stewart Attachment c:x:: u. s. Nuclear Regulatory o:mnissim Region II 101 Marietta street, N. W. SUite 2900 . Atlanta, GeoJ:gia 30323 Mr. W. E. Hollarn NRC Senior Resident Inspector SUrcy Pael:' station ~bJ0150243 871008 Q ADOCK 050002St PDR 1987 NRC ClHo!ENI':
Serial.No.  
DlrJ.DJ the Nuclear Regulato:cy o:,m,i ssion (NRC) inspection corxlucted on Noveni:>er 13-20, 1986 an::l Februa:cy 9, 1987, a violation of NRC requirements was
NO/En'S :vlh Dx:ket Nos. License Nos. 87-570 R3 50-280 50-281 m:R-32 DPR-37 We have reviewed ya.ir letter of Septeni:>er  
* identified.  
8, 1987, in refererx:e  
'!he violation involved failure to prq>erly establish ccnlitians to perfonn the Type A IlRI'. In acooi:darx:le with the "General statement of Policy ani Procedure for NRC Enforcement Acticms," 10 cm Part 2, AR;>ernix c (1986), the violatiai is listed below: 10 cm 50 AR;>ernix J, Paragrai:n II defines a Type A test as a test . interned to measure the primary containment overall integrated leakage rate obtained by a sumration of leakage thralgh
to the Notice of Violation  
* all potential leakage paths irx:l~ valves, fittin;Js  
is.sued with Inspection  
,--ani carp:>nents
Report 50-281/86-36  
* which
an Mardi 2, 1987. additional  
* penetrate contaimnent.
response to the Notice of Violation  
Paragraii1 III.A.1. (d) :requires that fluid systems that are part of the reactor coolant pressure bcurrlary an::l are directly to the oontai.rnnent at:IoosJ;nere tm:ler post-acx:ident oonlitions shall be q:ened or vented to the oontainnent a~ prior to an::l duri.rg the Type A test. All vented systems nust be drained of water to the extent necessacy to assure exposure of the contairment isolation valve to canta.i.nment air test pressure an::l to assure they will be subjected to the post-acx:ident differential pressure.
is in the attachment.  
systerrs that are nonnal.ly filled with water am operating un::ler post-acx:ident con:litions are not required to be vented; however, their c:x>ntairnnent isolation valves nust be Type C _tested. . Paragraiil III. c :requires that contairnnent isolation valves be Type C tested to neasure their leakage rate by pressurizin:J with air or nitrogen unless the valve is pressurized with fluid fran a seal system. Tedmical Specification, Table 3. 8-2, lists the contaimnent isolation valves ani specifies whidl ones are exenpt fran Type c testin:J.
We :request that ya.ir :reevaluatim  
SUdl exerption signifies that the valves have :received credit for a water seal ani are not CX11Siderm a credible leakage path for the oontainment atna;plere.
of this violation  
Table 3.8-2 irx:lmes the isolation valves for Penetrations No. 46, 63, an::l 66 through 71 ani does not exenpt them fran Type C testiDJ.
be postponed, perrlin;J  
* Calt:rai:y to the above, the licensee failed to either properly vent an::l drain Peneb:aticms No. 46, 63, 64, an::l 66 thralgh 71 durin;J the pe.rfcmnarx:ie of the NoYaliJer 1986,
resolution  
* Type A test ai Unit 2, or to d.etennine the overall integrated leakage rate by the sunmation of the leakages cbtained duriD:J the Type C testi.rg of such penetrations to the* results cbtained durin;J the CIIRl'. 'I.his is a Severity level 'IV violation (SUR;>lement I).
of the tedmical issue by NRR. '!he basis for our :request is provided in the attadmlent.  
* _ 1. Admission or denial of the alleged violation:
If you have arr:/ further questions, please contact. us. Very truly yoors, W. L. stewart Attachment  
We believe a differerx:e in intel:pretation has created an issue requirirg resolution by NRR. To :resolve this issue will* require a sul:lnittal to the Offiee of Nuclear . Reactor Regulation (NRR) for tedmical evaluatiai.
c:x:: u. s. Nuclear Regulatory  
Until that su1:lnittal an:i NRR's tectmical evaluation are ccuplete, '{,i,18 feel that your :reevaluation of the violation shcw.d be p:stpJned.
o:mnissim  
: 2. Reason for the violation:  
Region II 101 Marietta street, N. W. SUite 2900 . Atlanta, GeoJ:gia 30323 Mr. W. E. Hollarn NRC Senior Resident Inspector  
'lhe tedmical issue cited in the violation is the requirement to vent am drain penetrations durirg Type A leak rate testirg or il'ci.u:Je the c!R)rq>riate Type c leakage penalty. Yoor ootice of violation in:iicates that any penetration listed in Table 3. 8-2 of the Tedmical ~ifications subject to Type c testirg nust also be vented am drained durin:J the Type A test. SUdl a requirement is not fam in either 10 CFR 50 J or the Teclmical Specifications.
SUrcy Pael:' station ~bJ0150243  
Paragrapl III.A.1. (d) of~ J states that system; oonnally filled with water am q,eratin;J umer post-acx::ident c:on:litions need :oot be vented; l"lcMever, their containment isolation valves must be Type c tested. '!he contairnnent testirg of Unit 2 was in pliance with this requirement.
871008 Q ADOCK 050002St PDR
We believe a difference in the tion of the 10 CFR 50 J requirements has -created this unresolved tedmical issue
1987 NRC ClHo!ENI':  
* 3. '!he corrective steps that have been taken am the resu1 ts achieved:
DlrJ.DJ the Nuclear Regulato:cy  
To date no specific corrective actions have been taken. Telei;none calls to NRR am the Regional office have been initiated to disc,JSS the basis for the violation am the evaluation irx:hded in the enclosure to the NRC letter fran J. Nelson Grace to W. L. Stewart, dated September 8, 19_87. 4. '!he corrective steps that will be taken to avoid further violations:
o:,m,i ssion (NRC) inspection  
To prevent. further misurrlerst:aminJs in this
corxlucted  
* area, '\li,18 interrl to provide the technical basis for detennining that the specific penetrations in
on Noveni:>er  
* question do q,erate urner acx::ident ccnlitioos am are imee6 normally filled with water. '!he tedmical basis will be sul::mitted by Jarruary 30, 1988 in canjurction with a SUR>lement to oor July 23, 1987 Tedmical Specification sutmittal (Serial No. 87-375), whlch will anootate those valves :oot subject to C testin:J as 't,i,1811 as those valves which are q,erat.in:J umer acx::ident cc:nlitioos am are normally filled with water aIXl no Type C penalty required.
13-20, 1986 an::l Februa:cy  
Aalitionally, after the technical evaluation has been ccupleted by NRR loJe interrl to sul::mit an . exenption request the NcweniJer 1986, Type A "as-fc:un:l" test results for the next scheduled Type A test on unit 2. 5. '!he date when full cgrpliance will be achieved:
9, 1987, a violation  
Revisions to oor Type "A" Integrated leak Rate Test Program, will be made as required, after NRR's technical evaluation is ocmplete.}}
of NRC requirements  
was * identified.  
'!he violation  
involved failure to prq>erly establish  
ccnlitians  
to perfonn the Type A IlRI'. In acooi:darx:le  
with the "General statement  
of Policy ani Procedure  
for NRC Enforcement  
Acticms," 10 cm Part 2, AR;>ernix  
c (1986), the violatiai  
is listed below: 10 cm 50 AR;>ernix  
J, Paragrai:n  
II defines a Type A test as a test . interned to measure the primary containment  
overall integrated  
leakage rate obtained by a sumration  
of leakage thralgh * all potential  
leakage paths irx:l~ valves, fittin;Js  
,--ani carp:>nents  
* which * penetrate  
contaimnent.  
Paragraii1  
III.A.1. (d) :requires  
that fluid systems that are part of the reactor coolant pressure bcurrlary  
an::l are directly to the oontai.rnnent  
at:IoosJ;nere  
tm:ler post-acx:ident  
oonlitions  
shall be q:ened or vented to the oontainnent  
a~ prior to an::l duri.rg the Type A test. All vented systems nust be drained of water to the extent necessacy  
to assure exposure of the contairment  
isolation  
valve to canta.i.nment  
air test pressure an::l to assure they will be subjected  
to the post-acx:ident  
differential  
pressure.  
systerrs that are nonnal.ly  
filled with water am operating  
un::ler post-acx:ident  
con:litions  
are not required to be vented; however, their c:x>ntairnnent  
isolation  
valves nust be Type C _tested. . Paragraiil  
III. c :requires  
that contairnnent  
isolation  
valves be Type C tested to neasure their leakage rate by pressurizin:J  
with air or nitrogen unless the valve is pressurized  
with fluid fran a seal system. Tedmical Specification, Table 3. 8-2, lists the contaimnent  
isolation  
valves ani specifies  
whidl ones are exenpt fran Type c testin:J.  
SUdl exerption  
signifies  
that the valves have :received  
credit for a water seal ani are not CX11Siderm  
a credible leakage path for the oontainment  
atna;plere.  
Table 3.8-2 irx:lmes the isolation  
valves for Penetrations  
No. 46, 63, an::l 66 through 71 ani does not exenpt them fran Type C testiDJ. * Calt:rai:y  
to the above, the licensee failed to either properly vent an::l drain Peneb:aticms  
No. 46, 63, 64, an::l 66 thralgh 71 durin;J the pe.rfcmnarx:ie  
of the NoYaliJer  
1986, * Type A test ai Unit 2, or to d.etennine  
the overall integrated  
leakage rate by the sunmation  
of the leakages cbtained duriD:J the Type C testi.rg of such penetrations  
to the* results cbtained durin;J the CIIRl'. 'I.his is a Severity level 'IV violation (SUR;>lement  
I).
* _ 1. Admission  
or denial of the alleged violation:  
We believe a differerx:e  
in intel:pretation  
has created an issue requirirg  
resolution  
by NRR. To :resolve this issue will* require a sul:lnittal  
to the Offiee of Nuclear . Reactor Regulation (NRR) for tedmical evaluatiai.  
Until that su1:lnittal  
an:i NRR's tectmical  
evaluation  
are ccuplete, '{,i,18 feel that your :reevaluation  
of the violation  
shcw.d be p:stpJned.  
2. Reason for the violation:  
'lhe tedmical issue cited in the violation  
is the requirement  
to vent am drain penetrations  
durirg Type A leak rate testirg or il'ci.u:Je  
the c!R)rq>riate  
Type c leakage penalty. Yoor ootice of violation  
in:iicates  
that any penetration  
listed in Table 3. 8-2 of the Tedmical ~ifications  
subject to Type c testirg nust also be vented am drained durin:J the Type A test. SUdl a requirement  
is not fam in either 10 CFR 50 J or the Teclmical  
Specifications.  
Paragrapl  
III.A.1. (d) of~ J states that system; oonnally filled with water am q,eratin;J  
umer post-acx::ident  
c:on:litions  
need :oot be vented; l"lcMever, their containment  
isolation  
valves must be Type c tested. '!he contairnnent  
testirg of Unit 2 was in pliance with this requirement.  
We believe a difference  
in the  
tion of the 10 CFR 50 J requirements  
has -created this unresolved  
tedmical issue * 3. '!he corrective  
steps that have been taken am the resu1 ts achieved:  
To date no specific corrective  
actions have been taken. Telei;none  
calls to NRR am the Regional office have been initiated  
to disc,JSS the basis for the violation  
am the evaluation  
irx:hded in the enclosure  
to the NRC letter fran J. Nelson Grace to W. L. Stewart, dated September  
8, 19_87. 4. '!he corrective  
steps that will be taken to avoid further violations:  
To prevent. further misurrlerst:aminJs  
in this * area, '\li,18 interrl to provide the technical  
basis for detennining  
that the specific penetrations
in * question do q,erate urner acx::ident  
ccnlitioos  
am are imee6 normally filled with water. '!he tedmical basis will be sul::mitted  
by Jarruary 30, 1988 in canjurction  
with a SUR>lement  
to oor July 23, 1987 Tedmical Specification  
sutmittal (Serial No. 87-375), whlch will anootate those valves :oot subject to C testin:J as 't,i,1811  
as those valves which are q,erat.in:J  
umer acx::ident  
cc:nlitioos  
am are normally filled with water aIXl no Type C penalty required.  
Aalitionally, after the technical  
evaluation  
has been ccupleted  
by NRR loJe interrl to sul::mit an . exenption  
request the NcweniJer  
1986, Type A "as-fc:un:l" test results for the next scheduled  
Type A test on unit 2. 5. '!he date when full cgrpliance  
will be achieved:  
Revisions  
to oor Type "A" Integrated  
leak Rate Test Program, will be made as required, after NRR's technical  
evaluation  
is ocmplete.
}}

Revision as of 16:28, 31 July 2019

Responds to NRC 870908 Ltr Re Violations Noted in Insp Rept 50-281/86-36.Corrective Actions:Util Intends to Provide Technical Basis for Determining That Specific Penetrations Do Operate Under Accident Conditions & Filled W/Water
ML18151A106
Person / Time
Site: Surry 
Issue date: 10/08/1987
From: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
87-570, NUDOCS 8710150243
Download: ML18151A106 (3)


Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIBGINIA 23261 W. L. STBWABT VxcB PREBIDE>l'T NUCLBAB 0PEBAT10"8

  • October 8, 1987 U. s. Nuclear Regulatory O'mni ssim Attn: I)*x:nment cart:rol Desk Washirgtm, D.C.
  • 20555 Gentlemen:

VIRID{IA ET& :IRLC AND R'.JrlER SCllm RNm smTiaf tmTS 1 AND 2 . NRC INSPECl'Iaf REEtRl! R>. 50-28U86-36 Serial.No.

NO/En'S :vlh Dx:ket Nos. License Nos.87-570 R3 50-280 50-281 m:R-32 DPR-37 We have reviewed ya.ir letter of Septeni:>er 8, 1987, in refererx:e to the Notice of Violation is.sued with Inspection Report 50-281/86-36 an Mardi 2, 1987. additional response to the Notice of Violation is in the attachment.

We :request that ya.ir :reevaluatim of this violation be postponed, perrlin;J resolution of the tedmical issue by NRR. '!he basis for our :request is provided in the attadmlent.

If you have arr:/ further questions, please contact. us. Very truly yoors, W. L. stewart Attachment c:x:: u. s. Nuclear Regulatory o:mnissim Region II 101 Marietta street, N. W. SUite 2900 . Atlanta, GeoJ:gia 30323 Mr. W. E. Hollarn NRC Senior Resident Inspector SUrcy Pael:' station ~bJ0150243 871008 Q ADOCK 050002St PDR 1987 NRC ClHo!ENI':

DlrJ.DJ the Nuclear Regulato:cy o:,m,i ssion (NRC) inspection corxlucted on Noveni:>er 13-20, 1986 an::l Februa:cy 9, 1987, a violation of NRC requirements was

  • identified.

'!he violation involved failure to prq>erly establish ccnlitians to perfonn the Type A IlRI'. In acooi:darx:le with the "General statement of Policy ani Procedure for NRC Enforcement Acticms," 10 cm Part 2, AR;>ernix c (1986), the violatiai is listed below: 10 cm 50 AR;>ernix J, Paragrai:n II defines a Type A test as a test . interned to measure the primary containment overall integrated leakage rate obtained by a sumration of leakage thralgh

  • all potential leakage paths irx:l~ valves, fittin;Js

,--ani carp:>nents

  • which
  • penetrate contaimnent.

Paragraii1 III.A.1. (d) :requires that fluid systems that are part of the reactor coolant pressure bcurrlary an::l are directly to the oontai.rnnent at:IoosJ;nere tm:ler post-acx:ident oonlitions shall be q:ened or vented to the oontainnent a~ prior to an::l duri.rg the Type A test. All vented systems nust be drained of water to the extent necessacy to assure exposure of the contairment isolation valve to canta.i.nment air test pressure an::l to assure they will be subjected to the post-acx:ident differential pressure.

systerrs that are nonnal.ly filled with water am operating un::ler post-acx:ident con:litions are not required to be vented; however, their c:x>ntairnnent isolation valves nust be Type C _tested. . Paragraiil III. c :requires that contairnnent isolation valves be Type C tested to neasure their leakage rate by pressurizin:J with air or nitrogen unless the valve is pressurized with fluid fran a seal system. Tedmical Specification, Table 3. 8-2, lists the contaimnent isolation valves ani specifies whidl ones are exenpt fran Type c testin:J.

SUdl exerption signifies that the valves have :received credit for a water seal ani are not CX11Siderm a credible leakage path for the oontainment atna;plere.

Table 3.8-2 irx:lmes the isolation valves for Penetrations No. 46, 63, an::l 66 through 71 ani does not exenpt them fran Type C testiDJ.

  • Calt:rai:y to the above, the licensee failed to either properly vent an::l drain Peneb:aticms No. 46, 63, 64, an::l 66 thralgh 71 durin;J the pe.rfcmnarx:ie of the NoYaliJer 1986,
  • Type A test ai Unit 2, or to d.etennine the overall integrated leakage rate by the sunmation of the leakages cbtained duriD:J the Type C testi.rg of such penetrations to the* results cbtained durin;J the CIIRl'. 'I.his is a Severity level 'IV violation (SUR;>lement I).
  • _ 1. Admission or denial of the alleged violation:

We believe a differerx:e in intel:pretation has created an issue requirirg resolution by NRR. To :resolve this issue will* require a sul:lnittal to the Offiee of Nuclear . Reactor Regulation (NRR) for tedmical evaluatiai.

Until that su1:lnittal an:i NRR's tectmical evaluation are ccuplete, '{,i,18 feel that your :reevaluation of the violation shcw.d be p:stpJned.

2. Reason for the violation:

'lhe tedmical issue cited in the violation is the requirement to vent am drain penetrations durirg Type A leak rate testirg or il'ci.u:Je the c!R)rq>riate Type c leakage penalty. Yoor ootice of violation in:iicates that any penetration listed in Table 3. 8-2 of the Tedmical ~ifications subject to Type c testirg nust also be vented am drained durin:J the Type A test. SUdl a requirement is not fam in either 10 CFR 50 J or the Teclmical Specifications.

Paragrapl III.A.1. (d) of~ J states that system; oonnally filled with water am q,eratin;J umer post-acx::ident c:on:litions need :oot be vented; l"lcMever, their containment isolation valves must be Type c tested. '!he contairnnent testirg of Unit 2 was in pliance with this requirement.

We believe a difference in the tion of the 10 CFR 50 J requirements has -created this unresolved tedmical issue

  • 3. '!he corrective steps that have been taken am the resu1 ts achieved:

To date no specific corrective actions have been taken. Telei;none calls to NRR am the Regional office have been initiated to disc,JSS the basis for the violation am the evaluation irx:hded in the enclosure to the NRC letter fran J. Nelson Grace to W. L. Stewart, dated September 8, 19_87. 4. '!he corrective steps that will be taken to avoid further violations:

To prevent. further misurrlerst:aminJs in this

  • area, '\li,18 interrl to provide the technical basis for detennining that the specific penetrations in
  • question do q,erate urner acx::ident ccnlitioos am are imee6 normally filled with water. '!he tedmical basis will be sul::mitted by Jarruary 30, 1988 in canjurction with a SUR>lement to oor July 23, 1987 Tedmical Specification sutmittal (Serial No.87-375), whlch will anootate those valves :oot subject to C testin:J as 't,i,1811 as those valves which are q,erat.in:J umer acx::ident cc:nlitioos am are normally filled with water aIXl no Type C penalty required.

Aalitionally, after the technical evaluation has been ccupleted by NRR loJe interrl to sul::mit an . exenption request the NcweniJer 1986, Type A "as-fc:un:l" test results for the next scheduled Type A test on unit 2. 5. '!he date when full cgrpliance will be achieved:

Revisions to oor Type "A" Integrated leak Rate Test Program, will be made as required, after NRR's technical evaluation is ocmplete.