ML20235E898
| ML20235E898 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 09/16/1987 |
| From: | Johnston W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Heider L YANKEE ATOMIC ELECTRIC CO. |
| Shared Package | |
| ML20235E901 | List: |
| References | |
| NUDOCS 8709280312 | |
| Download: ML20235E898 (3) | |
See also: IR 05000029/1987007
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SEP 161987
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Dock &g>No.
50-29
License No. DPR-3
Yankee Atomic Electric Company
ATTN: Mr. L. H. Heider
Vice President of Operations
1671 Worcester Road
Framingham, Massachusetts 01701
Gentlemen:
Subject:
Inspection No. 50-29/87-07
This letter refers to the routine safety inspection conduce ed by
Ms. A. J. Lodewyk of this office on May 11-29, 1987 at Yankee Nuclear Power
Station and in the NRC Region I office.
Ms. Lodewyk discussed the inspection
findings with Mr. N. St.Laurent and other members of your staff at the con-
clusion of the onsite inspection, and during subsequent telephone discussions
between members of your staff and NRC regional and headquarters personnel.
This inspection focused on cycle XIX refueling outage activities regarding the
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facility steam generator surveillance inspection program.
Areas examined
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during this inspection are described in the NRC Region I Inspection Report
enclosed with this letter.
They included an on-site inspection of the steam
generator surveillance and maintenance programs; in-office review of related
Licensee Event Reports, proposed Technical Specifications, and surveillance
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test data; and, several conference calls regarding inspection results with
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licensee corporate and site representatives.
Based on our conversations, it
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is our understanding that you plan to take the following actions to improve
your inspection program.
1.
Develop and/or utilize inspection techniques with better capability to
characterize the nature and size (axial and circumferential directions)
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of the flaws being found in the Yankee Rowe S/Gs.
For example, follow-up
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inspections of degraded and defective tubes with a rotating pancake probe
and/or examination of tube specimens removed in the field.
2.
Propose a Technical Specification change to address issues such as full
length tube inspection and sample sizes (see Staff Recommendations in NRC Generic Letter 85-02).
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3.
Develop an inspection technique or plan to assure the tight radius U-bend
tubes receive complete inspection coverage. Also, consider entry from
both sides of a steam generator to ensure that tubes in rows 1-6 can be
inspected with full sized probes on both the hot and cold leg sides (also
see item 8 below).
4.
Update ECT manipulator and other steam generator inspection and mainte-
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nance equipment to reduce radiation exposures during inspection consistent
with ALARA goals (e.g., obtain a modified SM-10 manipulator to fit YNPS
S/G-and consider use of temporary, lead shields for S/G manways which
permit passage of ECT equipment
reference September 1986 INP0 report
titled "Swedish Experience in Reducing Occupational Radiation Exposure").
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5.
Increase involvement of experienced ECT personnel (i.e., Engineering /ISI
staff) in assuring quality of the spam generator inspection program.
6.
Ensure at least a secondary analysis will be completed for future ECT
data (reference EPRI guidelines for S/G inspections). Also, consider
(a) providing independent agency analyses or 3rd party review of data
and (b) perform onsite testing and qualification of analysts prior to
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performing outage activities.
7.
In reports to the commission, trend future data and attempt to quantify
the type and location of indications.
Trends will include rates of
degradation, changes in types, and increases / decreases in total number (s)
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of affected tubes.
8.
Review and implement (as appropriate for YNPS) the EPRI Guidelines for
Steam Generator Inspections and consider an inspection of all four S/Gs
at each inspection outage per the EPRI guidelines.
We request that you inform us if our understanding of your planned actions are
correct and provide us with a description of your plans in this area. Members
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of my staff will be available to discuss these issues and in particular proposed
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revised steam generator surveillance technical specifications at a mutually
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convenient time.
Based on the results of this inspection, it appears that one of your activities
regarding plugging of defective steam generator tubes was not conducted in full
compliance with NRC requirements, as set forth in the Notice of Violation,
enclosed herewith as Appendix A.
This violation has been categorized by se-
verity level in accordance with the " General Statement of Policy and Procedure
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for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (Enforcement Policy).
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You are required to respond to this letter and in preparing your response, you
should follow the instructions in Appendix A.
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OFFICIAL RECORD COPY
IR YANKEE 87-07 - 0002.0.0
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Yankee Atomic Electric Company
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The responses directed by this letter and the accompanying Notice are not
subject to the clearance procedures of the Dffice of Management and Budget
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as required by the Paperwork Reduction Act of 1980, PL 06-511.
Your cooperation with us in this matter is appreciated.
Sincerely,
Originni signed By1
Jacque P., D'arr
William V. Johnston, Acting Director
Division of Reactor Safety
Enclosures:
1.
Appendix A, Notice of Violation
2.
NRC Region I Inspection Report No. 50-29/87-07
cc w/encis:
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N. N. St. Laurent, Plant Superintendent
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J. E. Tribble, President
G. J. Papanic, Jr., Senior Project Engineer - Licensing
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Public Document Room (PDR)
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Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector
Commonwealth of Massachusetts (2)
bcc w/encls:
Region I Docket Room (with concurrences)
Management Assistant, DRMA (w/o encl)
DRP Section Chief
M. McBride, f,1, Pilgrim
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W. Raymond, SRI, Vermont Yankee
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M. Fairtile, LPM, NRR
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Robert J. Bores, DRSS
C. Y. Cheng, NRR
C. McCracken, NRR
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M. Shanbaky, DRSS
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