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{{Adams | |||
| number = ML20205G287 | |||
| issue date = 03/25/1987 | |||
| title = Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-029/86-17 | |||
| author name = Johnston W | |||
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) | |||
| addressee name = Heider L | |||
| addressee affiliation = YANKEE ATOMIC ELECTRIC CO. | |||
| docket = 05000029 | |||
| license number = | |||
| contact person = | |||
| document report number = NUDOCS 8703310418 | |||
| title reference date = 02-18-1987 | |||
| document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE | |||
| page count = 2 | |||
}} | |||
See also: [[see also::IR 05000029/1986017]] | |||
=Text= | |||
{{#Wiki_filter:_____-_m . __ _ ...m.__ _ _.__._..__; . _ , _ | |||
! MAR 2 5 1987 | |||
; | |||
' | |||
Docket No. 50-29 | |||
Yankee Atomic Electric Company | |||
l ATTN: Mr. L. H. Heider | |||
Vice President of Operations | |||
i 1671 Worcester Road | |||
2 | |||
Framingham, Massachusetts 01701 | |||
l | |||
l Gentlemen: | |||
: Subject: Inspection No. 50-29/86-17 | |||
This refers to your letter dated February 18, 1987, in response to our letter | |||
dated December 3, 1986. | |||
1 | |||
, | |||
Thank you for informing us of the corrective and preventive actions documented | |||
, in your letter. We found these actions to be responsive and consistent with | |||
, | |||
your previous discussions with our staff. The effectiveness of the | |||
implementation of these actions will be reviewed during future routine NRC | |||
; inspections. | |||
4 | |||
. Your cooperation with us is appreciated. | |||
! | |||
; Sincerely, | |||
j OM%1 g gn,4 gy , | |||
1 | |||
JCn11. Johnaon | |||
l William V. Johnston, Acting Director | |||
Division of Reactor Safety | |||
Enclosure: | |||
cc: | |||
N. N. St. Laurent, Plant Superintendent | |||
J. E. Tribble, President | |||
G. J. Papanic, Jr., Senior Project Engineer - Licensing | |||
' | |||
' | |||
Public Document Room (PDR) | |||
Local Public Document Room (LPDR) | |||
Nuclear Safety Information Center (NSIC) | |||
NRC Resident Inspector | |||
; Commonwealth of Massachusetts (2) | |||
1 | |||
8703310418 870325 | |||
PDR ADOCK 05000029 | |||
G PDR | |||
l | |||
, | |||
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Management Assistant, DRMA (w/o encl) | |||
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DRP Section Chief . * | |||
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M. McBride, SRI; Pilgrim ., ' | |||
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W. Raymond, SRI, Vermont 'tankee - | |||
, | |||
J. Clifford, LPM, NkR ' ' | |||
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Robert J. Bores, DRSS ,* i | |||
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OFFICIAL RECORD COPY | |||
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RL YANKEE 86-17 - 0002.0.0 l | |||
'. | |||
03/18/87 i | |||
1 | |||
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. . YANKEE ATOMIC ELECTRIC COMPANY | |||
. | |||
THOC 710-380 7619 | |||
,gstC----~=' gg | |||
1671 Worcester Road, Framingharrn, Massachusetts 01701 2.C2.11 | |||
[ [; M | |||
( ,b ANREE | |||
\ ' %. / February 18, 1987 | |||
FYR 87-017 ! | |||
- ;.- | |||
United States Nuclear Regulatory Commission | |||
Document Control Desk | |||
' | |||
Washington, DC 20555 | |||
References: (a) License No. DPR-3 (Docket No. 50-29) | |||
(b) I&E Letter to YAEC, I&E Inspection No. 50-029/86-17, | |||
dated December 3, 1986. | |||
d | |||
Subject: Response to Inspection 50-029/86-17 | |||
Dear Sir: | |||
.. | |||
Reference is made to I&E Inspection No. 50-029/86-17 conducted by Mr. Robert l | |||
W. Winters during the period September 29 through October 3, 1986, at the Yankee : | |||
Atomic Electric Company, Yankee Nuclear Power Station in Rowe, Massachusetts. ! | |||
The report made subsequent to that inspection identified several activities | |||
which apparently were not conducted in full compliance with NRC requirements. | |||
These activities constitute a single, severity level 4 violation which is com- | |||
prised of five items, each of which is discussed below. It was agreed that | |||
. the written response could be deferred, pending a discussion of these items. l | |||
This discussion was held on February 11, 1987 In accordance with Section 2.201 | |||
of the NRC's " Rules and Practices", Part 2, Title 10, Code of Federal Regulations, | |||
, | |||
we hereby submit the following information: | |||
' | |||
Apparent Violation | |||
Technical Specification 6.8.1 states in part: " Written procedures shall be | |||
established, implemented and maintained that meet or exceed the requirements | |||
and recommendations of Sections ... 5 3 of ANSI N18 7-1976...". ANSI N18.7 | |||
Section 5 3 requires procedures for safety-related activities including main- | |||
tenance, test and inspections. | |||
1 | |||
As of October 3, 1986, the implementation of procedures affecting safety-related ( | |||
caintenance, test and inspection activities were inadequate as evidenced by i | |||
the following examples: l | |||
l | |||
Item 1: AP-0205, " Maintenance Request", requires: | |||
a. That any maintenance performed on systems, components or | |||
structures that require quality assurance utilizing mater- | |||
ials, parts, replacement components or documentation shall | |||
necessitate the use of a Maintenance Request (MR), | |||
~ | |||
M N 6~f,d-3 d fd ~ D g g. | |||
_ _ _ _ _ _ _ _ _ _ _ _ ___ _ | |||
_ | |||
, _ , , | |||
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, . . 1 | |||
I | |||
' United States Nuclear Regulatory Commission | |||
Page 2 | |||
FYR 87-017 | |||
b. A description of the actual maintenance performed includ- | |||
ing procedurc number if applicable, | |||
c. A description of the retest performed and procedure used | |||
if applicable, | |||
d. A description of materials used including a description | |||
of the items or the Q/A or MI number and, , | |||
e. Completion of form APF-0205 2 for QA required MRs. | |||
. | |||
Contrary to the above: | |||
Several examples of alleged maintenance deficiencies were | |||
cited as examples of the above requirements not being met. | |||
Response to Item 1: | |||
Immediately following the identification of the apparent violation, | |||
the Maintenance Department evaluated the identified violations and, | |||
based upon the conclusions reached, discussed with maintenance per- | |||
sonnel the alleged violations, emphasizing the necessary actions and | |||
requirements of AP-0205 and reinforcing th. importance of adequate | |||
descriptions and attention to detail on the MR form. This process | |||
has been completed. | |||
The evaluation of the examples of the alleged maintenance deficiencies | |||
led to the conclusion that more attention must be provided in describing | |||
those actions taken on maintenance requests, with special attention | |||
given to the detaile of the problem and corrective action. To accom- | |||
plish this, programmatic procedure AP-0205 " Maintenance Requests" uill | |||
be revised to add guidance and clarification on the adequacy of detail | |||
necessary when initiating, performing,' completing and cancelling a | |||
maintenance request. In addition, Procedure OP-5103, " Inspection, | |||
Maintenance and Testing of Safety Relief Valve No. SV805", will be | |||
revised to include manufacturer's instructions, when applicable. Follow- | |||
ing these procedural revisions, training will be conducted for all | |||
appropriate maintenance and operations personnel. These activities | |||
will be completed by May 1, 1987 | |||
The 1987 audit and surveillance programs will include evaluations of | |||
the various plant functional areas to ensure that sufficient detail | |||
is provided in documenting all plant activities, and in identifying | |||
problems and delineating corrective actions. | |||
Item 2: Procedure AP-0209 states in part "... Inspection of safety-related | |||
activities shall be performed in accordance with approved written | |||
procedures, which set forth the requirements and acceptance limits | |||
and specify the inspection responsibilities ...". | |||
' | |||
_ | |||
. . . - . . - . ~ . - | |||
_ | |||
- ' | |||
. , | |||
' | |||
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, Unit:d Stat:a Nuclear Rigulat:ry Commission | |||
pig 2 3 | |||
FYR 87-017 | |||
Contrary to the above, the licensee's Quality Control (QC) inspections | |||
of safety-related activities, as documented in QCIRs 86-26, 86-33, | |||
86-54, 86-56, 86-181, 86-198, and 86-199 and others, were performed | |||
without utilizing approved written procedures which set forth the re- | |||
quirements, acceptance limits, and inspection responsibilities. | |||
Response to Item 2: | |||
Subsequent to the identification of this violation, Quality Control | |||
4 | |||
personnel were provided retraining with regard to procedure 0QA-X-5, | |||
' | |||
" Quality Control Inspections." Where QC Guidelines applied, their | |||
use was made mandatory; where Guidelines were not applicable, the QC | |||
Supervisor established proper inspection requirements and acceptance | |||
criteria. This action was completed on January 12, 1987 | |||
The Inspection Guidelines will be revised and used as " checklists". | |||
Their use will be made mandatory when performing inspections. These | |||
. will provide specific qualitative and quantitative acceptance criteria | |||
specific to the activity being performed. Procedure OQA-X-5 will also | |||
be resised to provide a mechanism for specifying appropriate QC inspection | |||
attributes for non-routine maintenance activities. These activities | |||
will be completed in conjunction with the procedural review discussed | |||
in response to Item 3, below. | |||
A revision to AP-0209 is in progress and will be completed by May 31, 1 | |||
1987 This revision will address internally generated QA audit deficien- | |||
cies as well as add clarifying statements regarding this NRC inspection. | |||
' | |||
Item 3: Procedure 0QA-X-5 states in part "... OQC personnel will review all | |||
Maintenance Requests (MR) to determine / establish the-following: ... | |||
hold points have been invoked as deemed necessary for inspection, based | |||
upon a review of repair plans or procedures; Notification points have | |||
been established to monitor specific facets of a process or repair | |||
" | |||
... . | |||
Contrary to the above, the licensee's QC group did not establish ho3d l | |||
points necessary for inspection based on a review of the repair plans | |||
and procedures to be used for each of the MRs. Rather than establishing | |||
specific hold points, the QC inspectors established notification points | |||
requiring notification prior to the start of work on all of the MRs | |||
reviewed. | |||
Response to Item 3: | |||
Procedure OQA-X-5 presently provides for the use of " Hold" or "Notifi- | |||
cation Points" without defining when each should be used. Guidelines | |||
will be established and will define the criteria for their use. In | |||
: addition, Procedure 0QA-1-5 will be revised to clarify the use of " Hold | |||
Points" and " Notification Points". This will be completed by May 1, | |||
1987 Quality control personnel will review Plant maintenance procedures | |||
and will evaluate the need for QC inspection " Hold Points". When deemed | |||
j- appropriate, these " Hold Points" may be introduced into those Maintenance | |||
Requests which call for the utilization of those procedures with the | |||
pre-established " Hold Points". This process will be completed within | |||
a 12-month period. | |||
, | |||
I | |||
* | |||
. | |||
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- - - - _ - _ _ _ _ _ _ _ _ .__ | |||
. | |||
_, | |||
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United States Nuclear Regulatory Commission | |||
Page 4 | |||
FYR 87-017 | |||
Item 4: Procedure OQA-I-5, regarding the final QC review, states in part, | |||
" ...Any deficiencies or deviations identified from the review shall | |||
be noted on the inspection form ...". | |||
Contrary to the above, the licensee's QC final review of the QCIRs | |||
was inadequate in that the QC inspectors failed to identify and document | |||
the aforementioned MR deficiencies and deviations (item 1 above) on | |||
the inspection form. | |||
Response to Item 4: | |||
, | |||
Inspection checklists will be developed for use in final reviews of | |||
' | |||
completed maintenance requests in order to improve the depth and con- | |||
l | |||
sistency of this portion of the inspection program. Quality control | |||
' | |||
inspectors will also be instructed in Maintenance Request and Proced- | |||
ural requirements to permit their evaluation of Maintenance practices. | |||
However, it will remain the responsibility of Maintenance supervision | |||
to determine the needs for Maintenance Requests and whether written | |||
procedures are required in accordance with AP-0205 and AP-0214. These | |||
actions will be completed by May 1, 1987 | |||
Item 5: The licensee's Equipment Classification Manual section 3 5 states: | |||
The requirements of the Yankee Atomic Operational Quality Assurance | |||
Manual (YOQAP-1-A) shall be applied to " . . . equipment . . . that: ... | |||
provide support to a safety system but are not covered by ... Safety | |||
Class (e.g. gaskets, packing, lubricants, etc.) ...". | |||
YOQAP-1-A Section VIII, states in part, "... The plant shall be re- | |||
sponsible for: ... the identification and control of materials ... | |||
storage of lubricants ... (and) maintenance of traceability of | |||
materials ... stored, installed and used in the plant ...". | |||
Contrary to the above, the requirements of YOQAP-1-A were not applied | |||
to turbine lubricating oil, used as hydraulic fluid providing support | |||
to safety systems, in that the licensee did not maintain the lubricant | |||
in accordance with the QA program requirements for controlling issuance | |||
and storage and maintaining traceability. | |||
Response to Item 5: , | |||
1 | |||
Future purchases of lubricating oils for safety-related equipment will | |||
be in accordance with the QA program. These lubricating oils will | |||
require a C of C and will be issued to the lube oil storage room to | |||
maintain traceability. Procedures will require that lubricating oil | |||
usage be logged upon withdrawal and that it be recorded, as applicable, | |||
on Maintenance Requests. These actions will be completed by May 1, | |||
1987 | |||
,. ' | |||
., | |||
,.. , | |||
United States Nuclear Regulatory Commission | |||
Page 5 | |||
FYR-87-017 | |||
We trust that you will find this information satisfactory; however, should you | |||
have any questions regarding this matter, please contact us. | |||
Very truly yours, | |||
YANKEE ATOMIC ELECTRIC COMPANY | |||
$ | |||
L. H. Heider | |||
Vice President and | |||
Manager of Operations | |||
LH/aed | |||
Attachment | |||
ec: USNRC Region 1 | |||
USNRC Resident Inspector, YNPS | |||
. -_ | |||
__. . . _ . | |||
}} |
Latest revision as of 03:28, 20 December 2021
ML20205G287 | |
Person / Time | |
---|---|
Site: | Yankee Rowe |
Issue date: | 03/25/1987 |
From: | Johnston W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
To: | Heider L YANKEE ATOMIC ELECTRIC CO. |
References | |
NUDOCS 8703310418 | |
Download: ML20205G287 (2) | |
See also: IR 05000029/1986017
Text
_____-_m . __ _ ...m.__ _ _.__._..__; . _ , _
! MAR 2 5 1987
'
Docket No. 50-29
Yankee Atomic Electric Company
l ATTN: Mr. L. H. Heider
Vice President of Operations
i 1671 Worcester Road
2
Framingham, Massachusetts 01701
l
l Gentlemen:
- Subject: Inspection No. 50-29/86-17
This refers to your letter dated February 18, 1987, in response to our letter
dated December 3, 1986.
1
,
Thank you for informing us of the corrective and preventive actions documented
, in your letter. We found these actions to be responsive and consistent with
,
your previous discussions with our staff. The effectiveness of the
implementation of these actions will be reviewed during future routine NRC
- inspections.
4
. Your cooperation with us is appreciated.
!
- Sincerely,
j OM%1 g gn,4 gy ,
1
JCn11. Johnaon
l William V. Johnston, Acting Director
Division of Reactor Safety
Enclosure:
cc:
N. N. St. Laurent, Plant Superintendent
J. E. Tribble, President
G. J. Papanic, Jr., Senior Project Engineer - Licensing
'
'
Public Document Room (PDR)
Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector
- Commonwealth of Massachusetts (2)
1
8703310418 870325
PDR ADOCK 05000029
G PDR
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1671 Worcester Road, Framingharrn, Massachusetts 01701 2.C2.11
[ [; M
( ,b ANREE
\ ' %. / February 18, 1987
FYR 87-017 !
- ;.-
United States Nuclear Regulatory Commission
Document Control Desk
'
Washington, DC 20555
References: (a) License No. DPR-3 (Docket No. 50-29)
(b) I&E Letter to YAEC, I&E Inspection No. 50-029/86-17,
dated December 3, 1986.
d
Subject: Response to Inspection 50-029/86-17
Dear Sir:
..
Reference is made to I&E Inspection No. 50-029/86-17 conducted by Mr. Robert l
W. Winters during the period September 29 through October 3, 1986, at the Yankee :
Atomic Electric Company, Yankee Nuclear Power Station in Rowe, Massachusetts. !
The report made subsequent to that inspection identified several activities
which apparently were not conducted in full compliance with NRC requirements.
These activities constitute a single, severity level 4 violation which is com-
prised of five items, each of which is discussed below. It was agreed that
. the written response could be deferred, pending a discussion of these items. l
This discussion was held on February 11, 1987 In accordance with Section 2.201
of the NRC's " Rules and Practices", Part 2, Title 10, Code of Federal Regulations,
,
we hereby submit the following information:
'
Apparent Violation
Technical Specification 6.8.1 states in part: " Written procedures shall be
established, implemented and maintained that meet or exceed the requirements
and recommendations of Sections ... 5 3 of ANSI N18 7-1976...". ANSI N18.7
Section 5 3 requires procedures for safety-related activities including main-
tenance, test and inspections.
1
As of October 3, 1986, the implementation of procedures affecting safety-related (
caintenance, test and inspection activities were inadequate as evidenced by i
the following examples: l
l
Item 1: AP-0205, " Maintenance Request", requires:
a. That any maintenance performed on systems, components or
structures that require quality assurance utilizing mater-
ials, parts, replacement components or documentation shall
necessitate the use of a Maintenance Request (MR),
~
M N 6~f,d-3 d fd ~ D g g.
_ _ _ _ _ _ _ _ _ _ _ _ ___ _
_
, _ , ,
- + > *
, . . 1
I
' United States Nuclear Regulatory Commission
Page 2
FYR 87-017
b. A description of the actual maintenance performed includ-
ing procedurc number if applicable,
c. A description of the retest performed and procedure used
if applicable,
d. A description of materials used including a description
of the items or the Q/A or MI number and, ,
e. Completion of form APF-0205 2 for QA required MRs.
.
Contrary to the above:
Several examples of alleged maintenance deficiencies were
cited as examples of the above requirements not being met.
Response to Item 1:
Immediately following the identification of the apparent violation,
the Maintenance Department evaluated the identified violations and,
based upon the conclusions reached, discussed with maintenance per-
sonnel the alleged violations, emphasizing the necessary actions and
requirements of AP-0205 and reinforcing th. importance of adequate
descriptions and attention to detail on the MR form. This process
has been completed.
The evaluation of the examples of the alleged maintenance deficiencies
led to the conclusion that more attention must be provided in describing
those actions taken on maintenance requests, with special attention
given to the detaile of the problem and corrective action. To accom-
plish this, programmatic procedure AP-0205 " Maintenance Requests" uill
be revised to add guidance and clarification on the adequacy of detail
necessary when initiating, performing,' completing and cancelling a
maintenance request. In addition, Procedure OP-5103, " Inspection,
Maintenance and Testing of Safety Relief Valve No. SV805", will be
revised to include manufacturer's instructions, when applicable. Follow-
ing these procedural revisions, training will be conducted for all
appropriate maintenance and operations personnel. These activities
will be completed by May 1, 1987
The 1987 audit and surveillance programs will include evaluations of
the various plant functional areas to ensure that sufficient detail
is provided in documenting all plant activities, and in identifying
problems and delineating corrective actions.
Item 2: Procedure AP-0209 states in part "... Inspection of safety-related
activities shall be performed in accordance with approved written
procedures, which set forth the requirements and acceptance limits
and specify the inspection responsibilities ...".
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FYR 87-017
Contrary to the above, the licensee's Quality Control (QC) inspections
of safety-related activities, as documented in QCIRs 86-26, 86-33,
86-54, 86-56,86-181, 86-198, and 86-199 and others, were performed
without utilizing approved written procedures which set forth the re-
quirements, acceptance limits, and inspection responsibilities.
Response to Item 2:
Subsequent to the identification of this violation, Quality Control
4
personnel were provided retraining with regard to procedure 0QA-X-5,
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" Quality Control Inspections." Where QC Guidelines applied, their
use was made mandatory; where Guidelines were not applicable, the QC
Supervisor established proper inspection requirements and acceptance
criteria. This action was completed on January 12, 1987
The Inspection Guidelines will be revised and used as " checklists".
Their use will be made mandatory when performing inspections. These
. will provide specific qualitative and quantitative acceptance criteria
specific to the activity being performed. Procedure OQA-X-5 will also
be resised to provide a mechanism for specifying appropriate QC inspection
attributes for non-routine maintenance activities. These activities
will be completed in conjunction with the procedural review discussed
in response to Item 3, below.
A revision to AP-0209 is in progress and will be completed by May 31, 1
1987 This revision will address internally generated QA audit deficien-
cies as well as add clarifying statements regarding this NRC inspection.
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Item 3: Procedure 0QA-X-5 states in part "... OQC personnel will review all
Maintenance Requests (MR) to determine / establish the-following: ...
hold points have been invoked as deemed necessary for inspection, based
upon a review of repair plans or procedures; Notification points have
been established to monitor specific facets of a process or repair
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... .
Contrary to the above, the licensee's QC group did not establish ho3d l
points necessary for inspection based on a review of the repair plans
and procedures to be used for each of the MRs. Rather than establishing
specific hold points, the QC inspectors established notification points
requiring notification prior to the start of work on all of the MRs
reviewed.
Response to Item 3:
Procedure OQA-X-5 presently provides for the use of " Hold" or "Notifi-
cation Points" without defining when each should be used. Guidelines
will be established and will define the criteria for their use. In
- addition, Procedure 0QA-1-5 will be revised to clarify the use of " Hold
Points" and " Notification Points". This will be completed by May 1,
1987 Quality control personnel will review Plant maintenance procedures
and will evaluate the need for QC inspection " Hold Points". When deemed
j- appropriate, these " Hold Points" may be introduced into those Maintenance
Requests which call for the utilization of those procedures with the
pre-established " Hold Points". This process will be completed within
a 12-month period.
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FYR 87-017
Item 4: Procedure OQA-I-5, regarding the final QC review, states in part,
" ...Any deficiencies or deviations identified from the review shall
be noted on the inspection form ...".
Contrary to the above, the licensee's QC final review of the QCIRs
was inadequate in that the QC inspectors failed to identify and document
the aforementioned MR deficiencies and deviations (item 1 above) on
the inspection form.
Response to Item 4:
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Inspection checklists will be developed for use in final reviews of
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completed maintenance requests in order to improve the depth and con-
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sistency of this portion of the inspection program. Quality control
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inspectors will also be instructed in Maintenance Request and Proced-
ural requirements to permit their evaluation of Maintenance practices.
However, it will remain the responsibility of Maintenance supervision
to determine the needs for Maintenance Requests and whether written
procedures are required in accordance with AP-0205 and AP-0214. These
actions will be completed by May 1, 1987
Item 5: The licensee's Equipment Classification Manual section 3 5 states:
The requirements of the Yankee Atomic Operational Quality Assurance
Manual (YOQAP-1-A) shall be applied to " . . . equipment . . . that: ...
provide support to a safety system but are not covered by ... Safety
Class (e.g. gaskets, packing, lubricants, etc.) ...".
YOQAP-1-A Section VIII, states in part, "... The plant shall be re-
sponsible for: ... the identification and control of materials ...
storage of lubricants ... (and) maintenance of traceability of
materials ... stored, installed and used in the plant ...".
Contrary to the above, the requirements of YOQAP-1-A were not applied
to turbine lubricating oil, used as hydraulic fluid providing support
to safety systems, in that the licensee did not maintain the lubricant
in accordance with the QA program requirements for controlling issuance
and storage and maintaining traceability.
Response to Item 5: ,
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Future purchases of lubricating oils for safety-related equipment will
be in accordance with the QA program. These lubricating oils will
require a C of C and will be issued to the lube oil storage room to
maintain traceability. Procedures will require that lubricating oil
usage be logged upon withdrawal and that it be recorded, as applicable,
on Maintenance Requests. These actions will be completed by May 1,
1987
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FYR-87-017
We trust that you will find this information satisfactory; however, should you
have any questions regarding this matter, please contact us.
Very truly yours,
YANKEE ATOMIC ELECTRIC COMPANY
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L. H. Heider
Vice President and
Manager of Operations
LH/aed
Attachment
ec: USNRC Region 1
USNRC Resident Inspector, YNPS
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