ML18151A106: Difference between revisions
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| issue date = 10/08/1987 | | issue date = 10/08/1987 | ||
| title = 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 | | title = 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 | ||
| author name = | | author name = Stewart W | ||
| author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) | | author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) | ||
| addressee name = | | addressee name = | ||
| Line 14: | Line 14: | ||
| page count = 3 | | page count = 3 | ||
}} | }} | ||
See also: [[ | See also: [[see also::IR 05000281/1986036]] | ||
=Text= | =Text= | ||
Revision as of 04:16, 17 June 2019
| 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) | |
See also: IR 05000281/1986036
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.