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{{Adams | |||
| number = ML20154J514 | |||
| issue date = 05/19/1988 | |||
| title = Forwards Notice of Violation & Notice of Deviation Re Insp Rept 50-285/88-10 on 880314-18.Documents Inadvertently Transmitted to Third Party One Day Before Rept Signed Out | |||
| author name = Milhoan J | |||
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) | |||
| addressee name = | |||
| addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) | |||
| docket = 05000285 | |||
| license number = | |||
| contact person = | |||
| document report number = NUDOCS 8805270025 | |||
| document type = INTERNAL OR EXTERNAL MEMORANDUM, MEMORANDUMS-CORRESPONDENCE | |||
| page count = 6 | |||
}} | |||
See also: [[see also::IR 05000285/1988010]] | |||
=Text= | |||
{{#Wiki_filter:2*# Wg, UNITED STATES | |||
! y% ' | |||
i , NUCLEAR REGULATORY COMMISSION | |||
h. . ,b REGION IV | |||
*,, 8 611 RYAN PLAZA DRIVE. SUITE 1000 | |||
k**"*8 | |||
, | |||
ARLINGTfN, | |||
MA I91988 TEXAS 79011 | |||
. | |||
' | |||
MEMORANDUM FOR: File | |||
FROM: James L. Milhoan, Director, Division of Reactor Safety | |||
SUBJECT: INADVERTENT RELEASE OF DRAFT MATERIAL | |||
The purpose of this memorandum is to place in the PDR copies of documents | |||
related to NRC Inspection Report 50-285/88-10. These documents were | |||
inadvertently transmitted via fascimile to a third party on April 18, 1988, | |||
the day before the report in question was signed out. | |||
M | |||
h James . lho n, Director | |||
T Division of Reactor Safety | |||
Enclosure: Ai stated | |||
cc w/ enclosure: | |||
R Martin, RIV | |||
v?DR 50-285 File Copy | |||
; | |||
\* | |||
k$$5270025880519 | |||
; o ADOCK 05000285 | |||
PDR | |||
.-, .--. . ._- | |||
. - , _ _ | |||
---. . .- - -. . .- | |||
' . | |||
, /' | |||
y T'< &, | |||
p WNitto sTAYts , | |||
. | |||
:. > - NUCLEAR REGULATORY COMMISSION ' I. | |||
' | |||
l mt010N IV I | |||
~ | |||
* | |||
* fit AY AN PL AZ A ORIVE. (Uif t 1000 l | |||
** * ARLINGTON. TEKAS M011 | |||
, ,, " | |||
. | |||
F ACSI'(ILE TRANSMITTAL | |||
0ATEtrivt: - | |||
/ff - _ | |||
PatentTY: | |||
Imeetately / | |||
1 Hout | |||
, | |||
2 4 Hours | |||
%: | |||
- QHbnd,d . O Ad4 A N | |||
W@A | |||
mtssact To: I | |||
Mtssast m ox: EAlf . 2 / L/ | |||
wumsEn Or PAaEs: Y Plus TRAxsMITTAL SHEET | |||
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TELECOPY NUMB | |||
-S Ol-752 YERIFICATION MUMBER: O /~ /[_ | |||
COMhCT: ' | |||
' | |||
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' | |||
, | |||
U | |||
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....................- m ...................................................... | |||
' | |||
SPECIAL INSTRUCTIONS / ATTACHMENT ($): | |||
, | |||
, | |||
, | |||
i | |||
l 1 | |||
................................... n ..............'.......................... | |||
. | |||
& Verified by: D15P0$!71'Gt: | |||
Trans tt' Return is %viginator V j | |||
dd @ 4 d Place b 4$.1 | |||
l | |||
! tdAME DATE Other _ | |||
i | |||
1 | |||
e . . | |||
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a- | |||
& | |||
, | |||
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, | |||
APPENDIX A | |||
_ NOTICE OF VIOLATION | |||
Omaha Public Power District | |||
Fort Calhoun Station Docket: 50-285 | |||
Operating License: DPR-40 | |||
During an NRC inspection conducted from March | |||
NRC requirements were identified. 14-18, 1988, two violations of | |||
resolve deficiencies identified during a surveillance test and failure | |||
licensee | |||
reactor coolant to verify | |||
systemthe | |||
leakcorrect | |||
test. qualifications for an examiner completing a | |||
Policy | |||
(1987), the and Procedure | |||
violations forbelow: | |||
are listed NRC Enforcement Actions " 10 CFR Part 2 | |||
A. | |||
Failure To Promptly Resolve Test Deficiencies , | |||
O | |||
quality assurance program requires that a test program sI | |||
established | |||
satisfactorily. to assure that . . . systems and components will perfonn ) | |||
documented | |||
satisfied. and evaluated to assure that test requirements ha | |||
i | |||
j | |||
Contrary to the above, Surveillance Test ST-NZ-1 was completed on May 8, i | |||
1987, with anamolies or deficiencies involving 11 nozzles. i | |||
There was not | |||
i an evaluation started of these anomalies or deficiencies | |||
1988. until March 15, | |||
This is a Severity Level IV violation. | |||
(SupplementI)(285/8810-01) | |||
B. j | |||
Failure | |||
Test Evaluationto Use Correct Qualification level of Examiner for Surveillance | |||
i | |||
Section 5.8.1 of the Technical Specifications (TS) requires that written | |||
procedures and administrative policies shall be established, implemented | |||
and 5.2 of ANSI N18.7-1972.and maintained that meet or exceed the minimum | |||
Table 1 of G-26 of the licensee's Standing | |||
Order G-26, R17. "Maintenance Quality Control Program," requires a minimum | |||
level II capability for personnel who evaluate and report test results. | |||
Contrary to the above, Surveillance Test ST-RLT-1, F.1 (leak test) results | |||
were evaluated and reported on May | |||
a lower capability level (Level 1). 29, 1987, by an individual qualified to | |||
This is a Severity Level IV violation. | |||
(SupplementI)(285/8810-02) | |||
i | |||
l | |||
5 | |||
. | |||
.J | |||
< | |||
. | |||
.., | |||
- O ^ | |||
2 | |||
Pursuant to the provisions of 10 CFR 2.201, Omaha Public Power District is | |||
hereby required to submit to this office, within 30 days of the date of the | |||
letter transmitting this Notice, a written statement or explanation in reply, | |||
including for each violation: (1) the reason for the violations if admitted, | |||
(2) the corrective steps which have been taken and the results achieved, | |||
(3) the corrective steps which will be taken to avoid further violations, and | |||
(4) the date when full compliance will be achieved. Where good cause is shown, | |||
consideration will be given to extending the response time. | |||
Dated at Arlington, Texas, | |||
this day of 1988. | |||
l | |||
l | |||
. | |||
. 3l | |||
. | |||
,e O | |||
f7 | |||
} ! | |||
! | |||
APPENDIX B ' | |||
NOTICE OF DEVIATION | |||
~0maha Public Power District Docket: 50-285 | |||
Fort Calhoun Station | |||
Operating License: DPR-40 | |||
Based on the results of an NRC inspection conducted from March 14-18, 1988, a | |||
deviation from your comitment was identified. | |||
The deviation consisted of | |||
failure to continue implementation of corrective actions comitted to in the | |||
response to an NRC violation. | |||
In accordance with the "General Statement of | |||
Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2 Appendix C | |||
(1987), the deviation is listed below: | |||
Failure to Continue Implementation of Corrective Actions | |||
Violation 285/8511-01, dated June 26, 1985, involved failure to account | |||
for six surveillance | |||
ending in July 1984,tests (STs), | |||
in the files.performed during the refueling outage | |||
The licensee's response to this | |||
violation stated, in part, "Each month the surveillance test clerk will | |||
issue a list of STs that are due but not filed and those due but not | |||
completed. | |||
Each | |||
indicating the supervisor | |||
status of each will | |||
test.be required to respond to this list by | |||
This status list will then be | |||
compiled and presented to the Plant Review Committee (PRC) by the | |||
Supervisor-Technical indicating those tests not completed /not filed and | |||
the action taken to assure completion / filing by the end of the next | |||
monthly review period." | |||
Contrary to the above, in deviation to that written comitment, a status | |||
list indicating the action taken to assure completion / filing by the end | |||
of the next monthly review period did not exist for a delinquent ST list | |||
dated March 2, 1988, which showed 11 STs dating from August 22, 1986, t | |||
through the end of the 1987 spring refueling outage, as being delinquent | |||
for filing. (285/8810-03) | |||
Omaha Public Power District is hereby requested to submit a written statement | |||
or explanation to this Office within 30 days of the date of the letter | |||
transmitting this Notice. This reply, should include for each deviation: | |||
(1) the reason for the deviation if admitted, (2) the corrective steps that | |||
have been taken and the results achieved. (3) the corrective steps that will be | |||
, | |||
taken to avoid further deviations, and (4) the date when full compliance will | |||
be achieved. Where good cause is shown, consideration will be given to | |||
extending the response time. | |||
> | |||
Dated at Arlington, Texas, | |||
this day of 1988. | |||
, | |||
] | |||
- | |||
O * | |||
@w[ | |||
/ | |||
of test results records for each procedure. The TS surveillance | |||
requirements or IST component together with the associated test procedures | |||
reviewed by the NRC inspector are tabulated in the Attachment. | |||
The NRC inspector determined that the required tests were being scheduled | |||
and performed as required in accordance with approved procedures. | |||
Acceptance criteria were specified in the procedures and, with the | |||
exceptions discussed below, the records stated satisfaction of acceptance | |||
criteria. Appropriate instructions for returning equipment to service | |||
following testing were given. Some problems involving failure to complete | |||
timely reviews of completed test records are discussed in Section 2.a. | |||
above and an example is given below. | |||
The NRC inspector discovered that completed Procedure ST-NZ-1, | |||
Section F.1, for flow testing containment spray nozzles noted anomalies | |||
and deficiencies which had not been formally reviewed and dispositioned. | |||
Specifically, it was noted that ten nozzles were not tested because of | |||
inaccessibility and that one nozzle was not working properly. The test had | |||
been completed on May 8, 1987, and was listed as delinquent for filing in | |||
the list updated on March 2, 1988. The failure to evaluate the anomolies | |||
or deficiencies with these nozzles is an apparent violation of 10 CFR i | |||
Part 50, Appendix B, Criterion XI, and the approved quality assurance I | |||
program. (285/8810-01) | |||
The NRC inspector discussed the deficiencies noted in the test record for | |||
ST-NZ-1 with plant management on March 15, 1988. The NRC inspector ! | |||
1 | |||
expressed concern that the plant was restarted with the operability of the | |||
containment spray system undetermined. A second conc. n expressed was | |||
that the licensee's administrative procedures for followup on test | |||
deficiencies were apparently not followed. The Supervisor-Maintenance | |||
initiated an Incident Report on March 16, 1988, to address the test | |||
problems noted. It contained the results of a preliminary safety analysis | |||
i | |||
which indicated that over 100 spray nozzles must be plugged before the i | |||
design flow rate of 5100 gpm would be decreased. The NRC inspector had no | |||
further safety concerns on this test. | |||
During the inspection, the NRC inspector requested records verifying the | |||
appropriate qualification level of examiners who completed reactor coolant | |||
system leak testing on May 29, 1987, and on June 1, 1987, in accordance | |||
with Procedure ST-RLT-1, Section F.1. Because these records were not made | |||
available prior to the exit, it was discussed as an unresolved item. | |||
Copies of qualification records were subsequently forwarded by the | |||
licensee to the NRC Region IV office on March 22, 1988. The qualification | |||
record for the examiner completing the test on May 29, 1987, indicated he | |||
had only an ANSI N45.2.6, level I qualification for hydrostatic testing. | |||
Paragr6ph F.1.b.(2)(a) of ST-RLT-1 states that examiners must be qualified | |||
in accordance with ASME Section XI, Article IWA-2000. Paragraph IWA-2212 | |||
of Article IWA-2000 requires the use of VT-2 visual examination for leak | |||
testing. Subarticle IWA-2300 requires qualification of personnel | |||
l | |||
- | |||
}} |
Latest revision as of 00:44, 15 November 2020
ML20154J514 | |
Person / Time | |
---|---|
Site: | Fort Calhoun |
Issue date: | 05/19/1988 |
From: | Milhoan J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
References | |
NUDOCS 8805270025 | |
Download: ML20154J514 (6) | |
See also: IR 05000285/1988010
Text
2*# Wg, UNITED STATES
! y% '
i , NUCLEAR REGULATORY COMMISSION
h. . ,b REGION IV
- ,, 8 611 RYAN PLAZA DRIVE. SUITE 1000
k**"*8
,
ARLINGTfN,
MA I91988 TEXAS 79011
.
'
MEMORANDUM FOR: File
FROM: James L. Milhoan, Director, Division of Reactor Safety
SUBJECT: INADVERTENT RELEASE OF DRAFT MATERIAL
The purpose of this memorandum is to place in the PDR copies of documents
related to NRC Inspection Report 50-285/88-10. These documents were
inadvertently transmitted via fascimile to a third party on April 18, 1988,
the day before the report in question was signed out.
M
h James . lho n, Director
T Division of Reactor Safety
Enclosure: Ai stated
cc w/ enclosure:
R Martin, RIV
v?DR 50-285 File Copy
\*
k$$5270025880519
- o ADOCK 05000285
.-, .--. . ._-
. - , _ _
---. . .- - -. . .-
' .
, /'
y T'< &,
p WNitto sTAYts ,
.
- . > - NUCLEAR REGULATORY COMMISSION ' I.
'
l mt010N IV I
~
- fit AY AN PL AZ A ORIVE. (Uif t 1000 l
- * ARLINGTON. TEKAS M011
, ,, "
.
F ACSI'(ILE TRANSMITTAL
0ATEtrivt: -
/ff - _
PatentTY:
Imeetately /
1 Hout
,
2 4 Hours
%:
- QHbnd,d . O Ad4 A N
W@A
mtssact To: I
Mtssast m ox: EAlf . 2 / L/
wumsEn Or PAaEs: Y Plus TRAxsMITTAL SHEET
-57)l-16Y-31fl
TELECOPY NUMB
-S Ol-752 YERIFICATION MUMBER: O /~ /[_
COMhCT: '
'
/ IMM bod kJ 7 2#-J/3/ .
'
,
U
>
....................- m ......................................................
'
SPECIAL INSTRUCTIONS / ATTACHMENT ($):
,
,
,
i
l 1
................................... n ..............'..........................
.
& Verified by: D15P0$!71'Gt:
Trans tt' Return is %viginator V j
dd @ 4 d Place b 4$.1
l
! tdAME DATE Other _
i
1
e . .
,.,---.------,,--,.-,,-,-....,-,,,,-,n,-,-,---,--c~-----n,, - - - - - . - - - -
__m ,
a-
&
,
f f
,
APPENDIX A
_ NOTICE OF VIOLATION
Omaha Public Power District
Fort Calhoun Station Docket: 50-285
Operating License: DPR-40
During an NRC inspection conducted from March
NRC requirements were identified. 14-18, 1988, two violations of
resolve deficiencies identified during a surveillance test and failure
licensee
reactor coolant to verify
systemthe
leakcorrect
test. qualifications for an examiner completing a
Policy
(1987), the and Procedure
violations forbelow:
are listed NRC Enforcement Actions " 10 CFR Part 2
A.
Failure To Promptly Resolve Test Deficiencies ,
O
quality assurance program requires that a test program sI
established
satisfactorily. to assure that . . . systems and components will perfonn )
documented
satisfied. and evaluated to assure that test requirements ha
i
j
Contrary to the above, Surveillance Test ST-NZ-1 was completed on May 8, i
1987, with anamolies or deficiencies involving 11 nozzles. i
There was not
i an evaluation started of these anomalies or deficiencies
1988. until March 15,
This is a Severity Level IV violation.
(SupplementI)(285/8810-01)
B. j
Failure
Test Evaluationto Use Correct Qualification level of Examiner for Surveillance
i
Section 5.8.1 of the Technical Specifications (TS) requires that written
procedures and administrative policies shall be established, implemented
and 5.2 of ANSI N18.7-1972.and maintained that meet or exceed the minimum
Table 1 of G-26 of the licensee's Standing
Order G-26, R17. "Maintenance Quality Control Program," requires a minimum
level II capability for personnel who evaluate and report test results.
Contrary to the above, Surveillance Test ST-RLT-1, F.1 (leak test) results
were evaluated and reported on May
a lower capability level (Level 1). 29, 1987, by an individual qualified to
This is a Severity Level IV violation.
(SupplementI)(285/8810-02)
i
l
5
.
.J
<
.
..,
- O ^
2
Pursuant to the provisions of 10 CFR 2.201, Omaha Public Power District is
hereby required to submit to this office, within 30 days of the date of the
letter transmitting this Notice, a written statement or explanation in reply,
including for each violation: (1) the reason for the violations if admitted,
(2) the corrective steps which have been taken and the results achieved,
(3) the corrective steps which will be taken to avoid further violations, and
(4) the date when full compliance will be achieved. Where good cause is shown,
consideration will be given to extending the response time.
Dated at Arlington, Texas,
this day of 1988.
l
l
.
. 3l
.
,e O
f7
} !
!
APPENDIX B '
NOTICE OF DEVIATION
~0maha Public Power District Docket: 50-285
Fort Calhoun Station
Operating License: DPR-40
Based on the results of an NRC inspection conducted from March 14-18, 1988, a
deviation from your comitment was identified.
The deviation consisted of
failure to continue implementation of corrective actions comitted to in the
response to an NRC violation.
In accordance with the "General Statement of
Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2 Appendix C
(1987), the deviation is listed below:
Failure to Continue Implementation of Corrective Actions
Violation 285/8511-01, dated June 26, 1985, involved failure to account
for six surveillance
ending in July 1984,tests (STs),
in the files.performed during the refueling outage
The licensee's response to this
violation stated, in part, "Each month the surveillance test clerk will
issue a list of STs that are due but not filed and those due but not
completed.
Each
indicating the supervisor
status of each will
test.be required to respond to this list by
This status list will then be
compiled and presented to the Plant Review Committee (PRC) by the
Supervisor-Technical indicating those tests not completed /not filed and
the action taken to assure completion / filing by the end of the next
monthly review period."
Contrary to the above, in deviation to that written comitment, a status
list indicating the action taken to assure completion / filing by the end
of the next monthly review period did not exist for a delinquent ST list
dated March 2, 1988, which showed 11 STs dating from August 22, 1986, t
through the end of the 1987 spring refueling outage, as being delinquent
for filing. (285/8810-03)
Omaha Public Power District is hereby requested to submit a written statement
or explanation to this Office within 30 days of the date of the letter
transmitting this Notice. This reply, should include for each deviation:
(1) the reason for the deviation if admitted, (2) the corrective steps that
have been taken and the results achieved. (3) the corrective steps that will be
,
taken to avoid further deviations, and (4) the date when full compliance will
be achieved. Where good cause is shown, consideration will be given to
extending the response time.
>
Dated at Arlington, Texas,
this day of 1988.
,
]
-
O *
@w[
/
of test results records for each procedure. The TS surveillance
requirements or IST component together with the associated test procedures
reviewed by the NRC inspector are tabulated in the Attachment.
The NRC inspector determined that the required tests were being scheduled
and performed as required in accordance with approved procedures.
Acceptance criteria were specified in the procedures and, with the
exceptions discussed below, the records stated satisfaction of acceptance
criteria. Appropriate instructions for returning equipment to service
following testing were given. Some problems involving failure to complete
timely reviews of completed test records are discussed in Section 2.a.
above and an example is given below.
The NRC inspector discovered that completed Procedure ST-NZ-1,
Section F.1, for flow testing containment spray nozzles noted anomalies
and deficiencies which had not been formally reviewed and dispositioned.
Specifically, it was noted that ten nozzles were not tested because of
inaccessibility and that one nozzle was not working properly. The test had
been completed on May 8, 1987, and was listed as delinquent for filing in
the list updated on March 2, 1988. The failure to evaluate the anomolies
or deficiencies with these nozzles is an apparent violation of 10 CFR i
Part 50, Appendix B, Criterion XI, and the approved quality assurance I
program. (285/8810-01)
The NRC inspector discussed the deficiencies noted in the test record for
ST-NZ-1 with plant management on March 15, 1988. The NRC inspector !
1
expressed concern that the plant was restarted with the operability of the
containment spray system undetermined. A second conc. n expressed was
that the licensee's administrative procedures for followup on test
deficiencies were apparently not followed. The Supervisor-Maintenance
initiated an Incident Report on March 16, 1988, to address the test
problems noted. It contained the results of a preliminary safety analysis
i
which indicated that over 100 spray nozzles must be plugged before the i
design flow rate of 5100 gpm would be decreased. The NRC inspector had no
further safety concerns on this test.
During the inspection, the NRC inspector requested records verifying the
appropriate qualification level of examiners who completed reactor coolant
system leak testing on May 29, 1987, and on June 1, 1987, in accordance
with Procedure ST-RLT-1, Section F.1. Because these records were not made
available prior to the exit, it was discussed as an unresolved item.
Copies of qualification records were subsequently forwarded by the
licensee to the NRC Region IV office on March 22, 1988. The qualification
record for the examiner completing the test on May 29, 1987, indicated he
had only an ANSI N45.2.6, level I qualification for hydrostatic testing.
Paragr6ph F.1.b.(2)(a) of ST-RLT-1 states that examiners must be qualified
in accordance with ASME Section XI, Article IWA-2000. Paragraph IWA-2212
of Article IWA-2000 requires the use of VT-2 visual examination for leak
testing. Subarticle IWA-2300 requires qualification of personnel
l
-