IR 05000029/1974012
| ML19339A413 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 10/01/1974 |
| From: | Haynes R, Sanders W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19339A412 | List: |
| References | |
| 50-029-74-12, 50-29-74-12, NUDOCS 8011030774 | |
| Download: ML19339A413 (6) | |
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U.S. ATO:!IC QCRGY CO:0!ISSIO::
D.IRECTORATE OF RECUL1 TORY OPE?ATIO::S,.
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REGION I
50-29/74-12 RO Inspection Report No:
Docket No:
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Licensec:
Yankee Atomic Electric Company License No:
20 Turnpike Road Priority:
C Westboro, Massachusetts 01581 Category:
Location:
Rowe, Massachusetts
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Typ'e of Licensee:
PWR 174 W(e)
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Special Announced Type of Inspection:
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L as of Inspection:
Sootember 18-19, 1974 Dates of Previous Inspection:
September 10-12. 1974 Reporting Inspector:
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i. dancers, Reactor inspector Date
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Accompanying Inspectorg; NGJE Date
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Other Accompanying Personnel:
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Rs.iewed By:
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l R. Haynes, Senior Reactor Inspector Date
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8013030'777
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s StBDIARY OF FI!!DI?;CS
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Enforcement Action
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None Licensee Action on Previously Identified Enforcement Itea Not Inspected
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Design Changes
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None i
Unusual Occurr^nces l
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i None Identified i
Other Significant Findings A.
Current Findings 1.
Corrective work has been completed on the safety injection systen pipe hanger # which had been displaced or damaged during
a water ha==er. vent.
(Details, Paragraph 3)
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The installation of hydraulic snubbers on the pressure relief piping of the pressurizer has been completed.
(Details, Paragraph 4)
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3.
The plant modifications, deemed necessary as a result of the evaluation of the effects of 5 piping system break outside containment, have been completed.
(Details, Paragraph 5)
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The Thin Wall Valve Verification Program as outlined in RO:I letter of June 22, 1972 has been completed.
(Details, Paragraph 2)
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Status of Previously Reported Unresolved Items Previous inspection in April, 1973, determined that (2) two valves required further evaluation to complete the " Thin Wall Valve Veri-fication Program". -This item is considered resolved.
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Manacement Interview
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At the co.:1usion of the inspection a meeting was held by the inspector with the following persons:
Yankee Atomic Electric Comoany
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W. Joner, Assistant Plant Superintendent J. Staub, Technical Assistant R. Durfey, Technical Assistant
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The following items were discussed:
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A.
Thin Wall Valve Verification Program. No deficiencies were identi-fied.
(Details, Paragraph 2)
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Safety injection system pipe hanger displacement and corrective work. No deficiencies were identified.
(Details, Paragraph 3)
C.
Installation of hydraulic snubber restraints ca the pressurizer relief valve lines. No deficiencies were identified.
(Details, Paragraph 4)
D.. Plant modifications for postulated effects of a piping system break. No deficiencies were identified.
(Details, Paragraph 5)
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DETAILS s
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Persons Contacted Yankee Atomic Electric Company
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W. Jones, Assistant Plant, Superintendent J. Staub, Technical Assistant R. Durfey, Technical Assistant D. Army. Engineering Assistant J. Singleton, Quality Assurance, Westboro, Massachusetts 2.
Thin Wall Valve Verification Program The program as outlined in letter June 22, 1972, from J. P. O'Reilly,
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was previously inspected in April of 1973.
The result of this inspection was approval of all of the valves with the exception of (2) two which required additional justification.
These were a motor operated 6" gate valve made by Pacific Valve Company and installed in the shutdown cooling line.
The other valve was a 4" Velan check valve in the safety injection system.
The inspector-reviewed the engineering evaluation for the acceptance of these two valves. This concludes the Valve Wall Verification Program. No deficiencies were identified.
3.
- Safety Injection System Pipe Hangers
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The hangers supporting the safety injection lines were displaced and bent as reported by Plant Information Report No. 18 which stated the cause to be attributed to a plant trip caused by an instrument electrical ground which resulted in auto-initiation of the safety injection system.
This caused a water han=er which resultedinashiftinthesafetyinjectionpipingsystemset.
The inspector reviewed the postulated causes and the corrective work performed which consisted of the following:
a.
Restoration and repositioning of restraints.
b.
Non-destructive testing of the hanger welds.
Non-destructive testing of welds of the low pressure safety c.
injection pipe penetration inside, the vapor containment, low pressure safety injection pipe penetration outside the vapor i
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containaent, high pressure safety injection pipc' penetration to pipe extension inside the vapor containment and high pressure safety injection extension pipe to vapor containment.
No deficiencies were identified.
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Pressurizer Relief Valve Discharge Lines An inspection was made of the work perfor=ed in the location and installation of hydraulic snubber restraints for the pressurizer relief valve discharge lines. This change was cade to meet the latest design criteria and to compensate for the maximum stress levels produced by transient dynamic loading during valve actua-tion. The following procedures and documentation were reviewed.
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OP-5000.15 - Instal'2 tion of pressurizer safety and relief valve discharge piping restraints b.
DP 5106 - Inspection and maintenance of hydraulic snubbers -
Grinnel.
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Inspection Check Lists j
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N.D.E. Procedure and results I
No deficiencies were identified.
5.
Plant Modifications
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The completed plant modificaticns, which were deemed necessary from
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J the study report of July, 1973, " Effects of a piping break outside
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containnent", were inspected for cdbpliance to the report. The
items inspected are listed:
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Switchgear room floor, the installed shield plates under the s.
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floor, added I beam restraints at feedwater line elbows, and protection of essential cable conduits feeding the switchgear room.
b.
Concrete wall between the turbine. hall mezzcnine and the switch-gear room, added restraint on adjacent feedwater line, added steel shield wall 32' long x 6' high between feedwater lines and wall, and steel door of switchgear room.
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Concrete wall containing a 8" x 16" plexiglas viewing winco.
between control room and turbine hall.
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d.
Modified doors to control room and switchgear reom.
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Crushable 14' x 14' impact liner place installed between the
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i main steam line and feedwater line and the outer vall of the
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switch gear room an,d restraints added to vital cable conduits 31' above the main steam line.
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f Within the scope of this inspection, no deficiencies were identified.
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