IR 05000029/1974004
| ML19339A401 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 05/09/1974 |
| From: | Davis A, Fasano A, Oberg C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19339A400 | List: |
| References | |
| 50-029-74-04, 50-29-74-4, NUDOCS 8011030766 | |
| Download: ML19339A401 (6) | |
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T U.S. ATOM,IC ENERGY CCT!ISSION
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DIRECTORATE OF REGULATORY OPERATIONS
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REGION I
50-99 / 7 t. -04
_ Docket No:. 50-29 RO Inspection Report No:
DPR-3 License No:
Yankee Atomic Electric Company Licensee:
20 Turnpike Road
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.riority:
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Category:
- Westboro, Massachusetts 01581 Rowe, Massachusetts __
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Location: _
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PWR, 600 MWt (1D
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Type of Licensce: __
Special, Announced Type of Inspection:
April 30 - May 2, 1074 tes of Inspection:
March 11-15, 1974
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Dates of Previous Inspection:
f/' 4/7/
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'Dm Reporting Inspector.:
c. n.Oberg ATauc1Pa1 qn=P ior Date Accompanying Inspectors:
Date Date
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Date
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_ ' / ate Other Accompanying Personnel:
A. B. Davis, Acting Operations D
Branch Chief N I[
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f Reviewed By:
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Acting Section Chie'f, IVR
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A. N. Fasano, l
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SUMMARY OF FIMDIMG9
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Enforcement Action None
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Licensee Action on Previously Identified Enforcement Action
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Not inspected Design Changes Not inspected
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Unusual Occurrences None
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Othe S,ignificant Findings
/. Urresolved Items None
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B.,
Current Findings
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1.
Refueling is scheduled for May 10 - July 3,1974.
2.
Refueling procedures have been' revised by the licensee.
(Para-graph 3)
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Management Interview Inspection findings concerning the following subjects were discussed with Messrs. Autio, Jones, and St. Laurent at t?e conclusion of the inspection on May 2, 1974:
A.
Purpose of Inspection The inspector stated that the purpose of the inspection was to follow up on the items related to refueling procedures which were identified in RO:I Inspection Report 50-29/74-02.
It was noted that not al.',
refueling procedures have been completely approved, but are scheduled to be prior to co=ceneccent of refueling operations.
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B.
Controlled Area for Refueling The inspector questioned the intent of the licensee in establishing an area.which would control entrance of personnel and materials to refueling operations area.
The licensee stated that an area would be established during re-fueling operations that would have limited access (work permit re-quired) and that would.be monitored by the assigned H. P. technician.
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C.
Personnel Indoctrination The inspector. questioned the licensee regarding containment integrity during refueling with specific interest in the equipment hatch and per.sonnel access hatch.
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The licensee stated the question would be investigated and that RO:I would be informed by telephone of the decision.
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NOTE: By a telephone call en May 3 the licensee stated that the equipnent hatch would be kept in place during refueling operations and that at least one door of the pcrsonnel hatch would be kept closca. These precautions are to be incorporated into the refueling procedut 3.
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" DETAILS
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Persons Contacted, Mr. H. Autio, Plant Superintendent Mr. W. Billings, Chemistry & Health Physics Supervisor Mr. T. Danck, Operations Supervisor Mr. M. Ebert, Reactor Engineer Mr. J. Flanigan, Plant Health Physicist Mr. W. Jones, Assistant Plant Superintendent Mr. N. St. Laurent, Technical Assistant to the Superintendent 2.
Operations The facility has been operating on a stretch-out program at about 70-65% nuclear power. Refueling is scheduled for May 10 - July 3, 1974.
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A tour of the facility, less containment, was made by the inspector.
No unusual conditions were noted and housekeeping was very satis-factory.
The shif t supervisor's log for the period March 11 - April 17 was reviewed by the inspector.
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3.
Refueling Procedures The inspector revieued the procedures listed below. The following comments were made to the licensee, a.
OP 1100.5 Dir. mantling and Reassembling of the Reactor Systems for Refueling (1) Determination of boron concentration did not agree with schedule in AP-9011.
Baron concentrations 'should be given in specific PPM units instead of shutdown margin units.
(2) Specific instruction for controlled area should be stated for material / tools accountability.
(3) If known, actual loops to be isolated should be stated in prerequis ites.
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(4) Use of temporary hatch cover was questioned.
(Resolved during management interview).
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l (5) Inspection of new fuel within specified time prior to fuel
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j loading was not stated. All.new fuel has been inspected.
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b.
OP-1000.10 Installation of Umbrella Clip Spacer Tubes in Irradiated Fuel No comments.
OP-4706 Shroud Tube Inspection c.
No comments, d.
OP-1209 Operation of the Manipulator Cranes, Handling Fixture and Transfer Equipment for Core - Refueling (1) Step #19 - Alarm setpoint should be specified.
(2) Step #5 - Statement was not clear.
(3) Step #27 - Determiniation as.to where and how the records
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for 1/m plot would be kept was not specified.
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(4) Page 19 (J) - Acceptance criteria for load lif t should be specified.
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OP-1214 Transfer of New Fuel from NFV (New Fuel Vault) to e.
SFP (Spent Fuel Pit)
(1) References (2) have been cancelled.
(2) SFP water limit not stated'.
i OP-1206 (Rev 1) Transfer of Spent Fuel Assemblies in Spent
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Fuel Pit using Manual Tool
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(1) References are not correct.
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i (2) Step '<3 requires action of last. step.
I (3) Reference to Refueling Accident Procedures (OP-3117) was I
not given.
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OP-3117RefuelingAccidents g.
(1)' Instructions to stop operations was not explicitly stated
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in Section A.
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(2) Sections D & E did not list dropping of a new or used fuel assembly as an indication of possible release of radioactive material.
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OP-3105 Emercency Eoron Inj ection No comments.
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OP-1202 Locked Valve List for Refueling No comn its.
j. AP-9011 Chemistry Test Frequencies and Specifications for Extended Shutdown
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No comments.
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OP-4812 Calibration Check of Canma Guards
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No comments.
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OP-4226 Testing of Fuel Handline "quinnent (1) Requirements for minimum testing period before refueling
was not specified.
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OP-4505 Inspection of Fuel Handling Ecuinnent
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No comments.
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OP-1000.5 Reactor Refueling and Component Inspection
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(1) Approved method for change to procedure should be referenced.
(2) Acceptance criteria for control / shim rod withdrawal should be specified. Action for sticking rod should be stated.
4.
Comments in RO:I Inspection Report 50-29/74-02 Comments given in paragraph L5 of the Inspection Report 50-29/74-02 have'been incorporated into revised refueling procedures. OP-1200, Reactor Fuel Loading, Component Replacement procedure has been can-celled, but comments have been included in replacement procedures.
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