IR 05000400/1981007
| ML18017B402 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 04/24/1981 |
| From: | Girard E, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18017B401 | List: |
| References | |
| 50-400-81-07, 50-401-81-07, 50-402-81-07, 50-403-81-07, NUDOCS 8106080053 | |
| Download: ML18017B402 (11) | |
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTAST., N.W., SUITE 3100 ATLANTA,GEORGIA 30303 Report Nos. 50-400/81-07, 50-401/81-07, 50-402/81-07, 50-403/81-07 Licensee:
Carolina Power and Light Company 411 Fayetteville Street Ral'eigh, NC 27602 Facility Name:
Harris Docket Nos. 50-400, 50-401, 50-402 and 50-403 License Nos.
CPPR-158, CPPR-159, CPPR-160 and CPPR-161 Inspection at Har is s te near Raleigh, North Carolina Inspect
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E. H. Gir rd Approved by: A...Herdt, Section Chief Technical Engineering Inspection Branch Engineering and Technical Inspection Division Da S gned Da e S gned SUMMARY Inspected.
on-April 7-10, 1981.
Areas-Inspected This. routine, announced inspection involved 26 inspector-hours onsite in the areas of licensee action on previous inspection findings (Units 1, 2, 3 and 4),
status of IE Bulletins (Units 1, 2,
and 4),
licensee identified items (50.55(e)) (Units 1, 2, 3 and 4), inspector follow-up items (Units 1,2, 3 and 4),
Audits (Units 1, 2,
and 4),
steel structures and supports observation of
.welding related activities (Unit 1)
and safety related piping '- observation of welding related activities (Unit 1).
Resul ts No items of noncompliance or deviation were identified.
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
"R.'M. Parsons, Site Manager
"G. L. Forehand, Director QA/QC.
, "A. M. Lucas, Senior Resident Engineer
- N. J. Chiangi, Manager, Engineering and Construction QA
"R. Hanford, Principal Engineer, NPCD
- I. A. Johnson, Principal QA Specialist
- T. J. Wait, QA/QC Specialist, Welding E. Betz., Senior QA-Specialist, NDE W. Mercer; Welding QA Other Organizations
- W. D. Goodman, Project Manager, Daniel Construction Company NRC Resident Inspector
"G. F. Maxwell
"Attended exit interview 2.
Exit Interview The inspection scope and findings, were summarized on April 10, 1981, with those persons indicated in paragraph 1 above.
3.
Licensee Action on Previous Inspection Findings (Units 1, 2, 3 and 4)
'a ~
(Closed)
Violation (400/80-27-02; 401-403/80-25-02):
Inadequate Procedures for Welder Qualification.
Carolina Power and Light Company's (CP&L's) letter of response dated March 11, 1981, has been reviewed and determined to be acceptable by Region II.
The inspector discussed the matter with site QA personnel and examined the corrective actions as stated in the letter of response.
Revisions to the applic-able site procedure (MP-02R8)
and its implementation in the weld test shop were verified.
This item is closed.
b.
(Closed)
Infraction (400/80-18-02):
Weld Material Control.
CPS L'
letter of response dated September 19, 1980, has been reviewed and determined acceptable by Region II.
The inspector discussed the matter with site QA personnel and verified performance of the corrective
C.
actions stated in the letter of response through a review of Field Change Request W-035, Deficiency and Disposition Report (DDR) 437 and training records.
This item is closed.
(Closed)
Deficiency (400/80-18-03):
Welder Per formance Qualification Records.,
CPKL's letter. of 'response, dated September 19, 1980-has been reviewed and determined acceptable by Region II.
The i.nspector, dis-cussed the matter with site, gA personnel and verified the corrective, actions. stated in the letter of response through documentation review, includihg a review of performance. qualification records for welders identified C-73'and C-56.
This item is closed.
4.
Unresolved Items Unresolved items are matters about which-more information is required to determine whether they are acceptable or may involve violations or devia-tions.
A new unresolved item identified during this inspection is discussed in. paragraph 8..
5.
Status of Inspection and Enforcement. Bulletins (IEB's) (Units 1,
2, 3,
and 4)
a.
(Open)
IEB 400,. 401/80-BU-21:
Valve Yokes Supplied by Mal'colm Foundry Company, Inc..
b.
CPKL'ubmitted their initial response to this bulletin to Region II in a, letter, dated January 5,
1981.
The response indicated that they have
.in storage for installation in Units
and 2; four active safety
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related valves containing yokes-manufactured by Malcolm Foundry.
In addition the.. letter stated that: they have 40 active safety related valves.-with-handwheels.manufactured by Malcolm Foundry.
I The HRC inspector reviewed CP&L'
DDR 516 which documents the poten-tially. defective valve yokes" for control and'isposition.
The licensee stated that the valves with handwheels,cast by Malcolm Foundry had not been recorded on a
DDR for disposition as there did not appear to be any safety significance implied for these items.
The inspector examined the valves with Malcolm cast yokes and verified proper tagging for control.
The disposition of these valves had not yet been specified.
Region II will examine disposition of the potentially defective valve yoke castings in subsequent inspections to verify performance of the actions requested'in the bulletin.
(Closed)
IEB 402, 403/80-BU-21:
Valve Yokes Supplied by Malcolm Foundry Company, Inc.
The licensee's response letter, referenced in 5.a above, indicated it was a response for all four units.
It only identified valves for Units 1 and 2 as containing parts cast by Malcolm Foundry. It was implied,
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but not specifically stated, that the active valves for Units 3 and
did not contain parts cast by Malcolm.
The inspector questioned the licensee on this and was informed that the active valves for Units
and 4 did not contain parts. cast. by Malcolm.
The inspector has no further questions on this item.
Within the areas examined, no vi'olations or deviations were identified.
Licensee Identified Items (50.55(e)) (Units 1, 2, 3 and'4)
a-.
b.
(Open)- Item 400, 401/79-14-01; 402, 403/79-13-01:
Improper Welds on Engineered Embedment-Plates The NRC inspector discussed the status of this item with the licensee.
The 1'icensee.
stated that they had not. completed their final checks to assure that the corrective; action for this item was complete.
The licensee DDR covering, this item.was identified as No. 269.
(Open) Item 400/80-23-11 Pipe Hanger Deficiencies n
,
The NRC inspector discussed this item with the licensee and was informed that, they anticipated that a final report for this item would be provided to NRC Region II by May 1, 1981.
The, DDR for this item was identified as No. 457.
Inspector Follow-'up Items (Units 1, 2, 3 and 4)
a.
b; (Closed)
item 400,, 401/79-26-02:
Surveillance of Contractor gA/gC.
Activities"..
The. inspector reviewed the licensee's procedure CgA-20 RO for surveillance of contractor welding and related activities and examined copies of'urveillances performed.
The inspector has no further questions. on this item, (Closed)
Item 400/80.-23-08; 401-403/80-21-08:
Records of Qualification Test Specimens.
The inspector discussed this item with the licensee's Level III'DE examiner and reviewed record descriptions prepared for the qualification test samples.
The inspector has no further questions on this matter.
C.
(Open) Item 400/80-27-09:
Placement of Lead Letter B on Film Cassette.
The inspector reviewed the current requirements for placement of the lead letter B as described in the licensee's procedure for radiographic examination, NDEP-101 RO.
, This matter was discussed with the licensee's Level III NDE examiner.
This item will.remain open for further review in subsequent NRC inspection.
Audits (Units 1, 2, 3 and 4)
The NRC inspector reviewed selected areas of the licensee's audit reports to determine compliance with regulatory requirements.
The portions of the reports selected by the inspector were those which addressed Criterion IX of 10CFR50. Appendix B.
9.
The audit. reports examined in these reviews were identified gAA/81-10 through 81-14, gAA/170-1 through 170-4-and gAA/175-1.
The inspector noted that the. audits appeared to be directed entirely towards documentation rather than work and, therefore, did not appear to adequately address the proficiency of personnel in the performance of special processes.
The inspector identified this unresolved item 400/81-07-01, Audits.
Within the areas examined, no violations or deivations were identified.
Steel Structures and Supports Observation of Welding Related Activities (Unit 1.)
The inspector observed welding related activities for steel structures and supports within the containment to verify compliance with regulatory requirements and licensee commitments.
The activities observed are as follows:
a.
Welding Welding was. observedin progress on containment penetration weld joints C1-271-M-5'-FPP and Cl-271-M-6-FPP.
The code applicable to these welds is ASME.Section III. (74W76),.
The welding was observed for use of welding control/record document (WDR),, proper weld identification/
location availability of work instructions, proper welding procedure, welding. technique adhered to,, specified base and. weld materials used, proper. joint geometry and cleanliness, acceptable welding environment, preheat and'interpass temperatures as specified, equipment in'ood condition and adequate records:
In verifying the 2504F preheat speci-fied for joint Cl-271-M-6-FPP on the WDR the inspector found that the personnel responsible for maintaining the preheat had crayons for verifying 200 F and 300'F temperatures but none for 250'F.
By use of the crayons the inspector found that the preheat at the subject weld joint exceeded 200'F but was less than 300'F.
The licensee subse-quently informed the NRC inspector that the code only required a 200 F
preheat for the weld rather than the 250'F specified.
The inspector indicated his concern for proper preheat specification and control and identified this as inspector follow-up item 400/81-07-02, Preheat.
b.
Welding Material Control The NRC inspector observed storage and handling of welding material at.
weld C1-271-M-5-FPP and the welding material issue stations to assure that it was properly corrtrolled, issued and identified until consumed in accordance with code requirement c.
Weld Heat Treatment The inspector observed post weld heat treatment in progress on weld 7-E8-371L-A for proper instrumentation for heat cycle recording, calibration of instruments, placement of thermocouples, temperature and holding time. as. specified,. temperature cycle, and records.
The code applicable to this weld is AWS D1.1-77.
Within the areas examined, no violations or deviations were identified.
10.
Other Safety Related Piping - Observation of Welding Activities (Unit 1)
e The NRC inspector observed'welding activities on safety related piping other than reactor coolant pressure boundary piping for compliance with NRC requirements and licensee commitments.
The applicable code. for this piping is ASME Section III (74 W76).
The. activities observed are as follows:
a.
Welding The inspector observed wel'ding in progress on joint. 1-CT-16-FW-89 (16" Dia X.375 wall, containment'spray system)
for use of WDR, proper weld location, availability of work instructions, proper joint preparation, acceptable environmental conditions, welder identified, adequately qualified inspection personnel, and adequate records.
b.
Welding Material Control The inspector:observed,the storage and handling of welding material for the. joint: identified in 10.a above. to assure that it was properly controlled, issued.and identified until consumed.
C.
Visual Examination of Welds The inspector observed final visual inspection of the following com-ponent. cooling system weld joints for proper verification of location, size, surface finish and absence.,of surface defects:
Weld Joint'"CC 166-1-SW-1 1-CC 138-2,"SW-1
~Pi e Size Welder Identified 18" Dia. x.375" wall B"10 18" Dia. x.375" wall C-89 d.
Welder gualification The inspector reviewed the performance qualification test record and welder qualification status list to verify the current qualification of welder C-8 e.
Nondestructive Examination The NRC inspector observed magnetic particle examination on weld 1-SW-48-FW-33 (30" Dia.
x 375" wall, service water system) for proper surface preparation and performance of the examination, Within the areas examined, no. violations or deviations were identifie ~I I
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