IR 05000400/1986029
| ML18019A838 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 05/15/1986 |
| From: | Blake J, Kleinsorge W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18019A837 | List: |
| References | |
| 50-400-86-29, NUDOCS 8606020330 | |
| Download: ML18019A838 (20) | |
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+**y0 UNITEDSTATES NUCLEAR REGULATORY COMMISSION REGION
101 MARIETTASTREET, N.W.
ATLANTA',GEORGIA 30323 Report No.:
Licensee:
50-400/86-29
Carolina Power and Light Company P. 0.
Box 1551 Raleigh, NC 27602 Docket No.:
50-400 Facility Name:
Harris
Inspection Con uct
- g+p 1-25, 1986 Inspector:
s rg Approved by:
J. J.
B a e, Section C lef Engineering Branch Division of Reactor Safety License No.:
CPPR-158 I~ViEC at lgne
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e Sl ne SUMMARY Scope:
This routine, unannounced inspection entailed 36 inspector-hours on site in the areas of housekeeping (54834B),
material identification and control (42902B), material control (429408),
reactor vessel intervals, safety related heating, ventilating and air conditioning (HVAC) systems (50100),
licensee identified items (50.55(e))
and inspector followup items (92701B).
Results:
No violations or deviations were identified.
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REPORT DETAILS Persons Contacted Licensee Employees
- J. L. Harress, Assistant Plant General Manager
- G. L. Forehand, Director of Quality Assurance/Quality Control (QA/QC)
- R. Hanfor d, Milestone Completion
- D. A. McGaw, Superintendent, QA/QC
- M. D. Vernon, Superintendent, QC Other licensee employees contacted included construction craftsmen, engineers, technicians, and office personnel.
Other Organization
- 0. F. Painter, Manager Westinghouse (W)
NRC Resident Inspectors
- G. F. Maxwell
- S. P. Burris
- P.
G.
Humphrey
- Attended exit interview Exit Interview (307038)
The inspection scope and findings were summarized on April 25, 1986, with those persons indicated in paragraph above.
The inspector described the areas inspected and discussed in detail the inspection findings listed below.
No dissenting comments were received from the licensee.
(Open)
Inspector Followup Item 50-400/86-29-01:
Release,"
paragraph 6c(l)
(Open)
Inspector Followup Item 50-400/86-29-02:
Exceptions,"
paragraph 7b(1)(a)
(Open)
Inspector Followup Item 50-400/86-29-03:
Documentation,"
paragraph 7b(l)(b)
(Open)
Inspector Followup Item 50-400/86-29-04:
Qualification Test Results,"
paragraph 7b(l)(c)
"Internals Qual ity
"Incomplete HEPA Filter
"Activated Charcoal (Open)
Inspector Followup Item 50-400/86-29-05:
"Char coal Filter Design Data," paragraph 7b( l)(d)
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(Open)
Unresolved Item 50-400/86-29-06:
"Charcoal Batch Volume," para-graph 7.b(1) (e)
The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspection.
3.
Licensee Action on Previous Enforcement Matters (92701B)(92702B)
Not inspected.
4.
Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve violations or deviations.
New unresolved items identified during this inspection are discussed in paragraph 7b(1)(e).
5.
Independent Inspection Effort Housekeeping (54834B),
Material Identification and Control (42902B)
and Material Control (42940B)
The inspector conducted a general inspection of power block to observe activities such as housekeeping, material identification and control; material control, and storage.
Within the areas examined, no violations or deviations were identified.
6.
Reactor Vessel Internals a ~
Review of guality Assurance Implementing Procedures (50061B)
The inspector reviewed the below listed documents to determine whether appropriate and adequate procedures as included or referenced in the gA manual to assure that activities associated with reactor vessel internals were controlled and performed according to NRC requirements and SAR commitments.
Particular attention was given to determine whether provisions had been established to assure conformance applicable requirements for the following activities:
Crane Testing and Vessel Intervals Lifting; internals installation inspection; and post installation activities.
CPSL-WP-06 Rev.
CPSL-WP-136 Rev.
CPSL-WP-135 Rev. I
'nspection and Testing of Hoisting Equipment and Rigging Used in WP-7 "Special Lifts"'Erection of Upper and Lower Reactor Vessel Internals Lift Rig"
"Internals Handling During Assembly and Fitup"
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CP&L-WP-7 Rev.
CP&L-WP-07 App. 1, Rev.
CP&L-WP-07 App. 2, Rev.
CP&L-WP-07 App. 3, Rev.
CP&L-WP-07 App. 12, Rev.
CP&L-WP-07 APP.
14, Rev.
CP&L-WP-07 App. 15, Rev.
CP&L-WP-07 App. 16, Rev.
CP&L-AP-XIII-07 Rev.
CP&L-TP-06 Rev.
W-2463A54-G01 Rev.
CP&L-AP-XIII-05 Rev.
CP&L-WP-105 Rev.
CP&L-WP-106 Rev.
CP&L-CM-M0094 Rev.
CP&L-CM-M0093 Rev.
CP&L-MMM-011 Rev.
"Large Vessel and Equipment Off Loading Procedure"
"Off Loading Lower Reactor Internals"
"Off Loading The Reactor Upper Internals"
"Reactor Closure Head Off Loading"
"Lifting Upper Internals for Storage Stand Removal"
"Transporting CTL Upper Internals to Containment Building"
"Transporting CTL Lower Internals to Containment Building"
"Removing CgL Lower Internals from Containment Building"
"In-Storage Inspections and Maintenance
"Measurement of Lower Internals"
"Reactor Internals Assembly (3-Loop Plants)"
"Material Storage"
"Installation of Equipment"
"Maintenance/Protection of Permanent Plant Equipment"
"Integrated Reactor Vessel Head and Upper Internals Removal"
"Corrective Maintenance"
"Cleanl ines s and Housekeeping"
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b.
Observation of Work and Work Activities (50063B)
The inspector observed reactor vessel internals protection activities in containment with the internals removed from the vessel to determine the following:
whether procedures for protection of the installed vessel internals are being followed; whether protective devices are installed around top of open vessel to prevent entry of foreign objects and debris into the vessel internals; whether vessel side openings are blanked off to prevent entry of foreign objects; whether access control is provided to assure only authorized entry of tools, equipment, and personnel and; whether cleanliness requirements are being met.
c.
Review of guality Records (50065B)
( 1)
The inspector reviewed pertinent quality records associated with vessel internals handling and installation to ascertain whether the established scope of quality assurance activities relative to handling, installation and inspections, including gA audits, was completed; and the work and inspection records confirm that the installation of the reactor vessel internals was in accordance with specifications and procedures.
With regard to the above, the inspector noted that W has not completed their post 'h'ot functional inspection of the reactor internals and thus, has not provided the licensee with a quality release for the same.
Pending NRC review of the above quality release, this matter will be identified as inspector followup item 50-400/86-29-01:
"Internals guality Release."
(2)
The inspector reviewed selected quality related records relative to post-installation vessel internals protection to ascertain whether the records confirm that:
adequate access control was provided; and required cleanliness of vessel internals was maintained.
Within the areas examined, no violations were identified.
7.
Safety-Related Heating, Ventilating, and Air Conditioning (HVAC) Systems (50100)
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The inspector reviewed quality assurance (gA) plans, instructions, and procedures for inspection of safety-related heating, ventilating, and air conditioning (HVAC)
systems to determine whether they (plans instructions and procedures)
were consistent with commitments and regulatory commitments.
The inspector reviewed the below listed documents to determine whether adequate inspection procedures had been established for HVAC activity; provisions had been made to ensure that those engaged in conducting inspections are qualified and have been adequately trained; means had been established to verify that the technical requirements had been
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specified in and were subsequently, extracted from the design and procurement documents and included in appropriate work and QC inspection procedures; means had been established to verify that any significant design and field changes from approved drawings were adequately controlled and processed commensurate with the original design; provisions had been established to ensure that quality requirements were met; safety-related/nonsafety-related boundaries and equipment were clearly defined and delineated.
CQC-6, Rev.
AP-XII-04 WP-402, Rev.
WP-403, Rev.
WP-404, Rev.
CQC-24, Rev.
AP-IX-05 CQC-18, Rev.
MMM-001, Rev.
CQA-l, Rev.
NDEP-10, Rev.
"Receiving Inspection"
"Purchasing Bolting Materials"
"Installation of Ductwork and Supports"
"Duct Work Leak and Pressure Tests"
"HVAC Work Package Generator"
"HYAC Ductwork Leak and Pressure Test Inspection"
"Field Change Request (FCR/PW)"
"Weld Control for Seismic Class 1 and Seismically Design Structural (Reg.
Guide 1.29) Weldments"
"Maintenance Management Manual"
"Personnel Training and Qualification"
"Training, Qualification and Certification of NDE Personnel" QCI-18.1, Rev.
QCI-18.3, Rev.
QCI-18.6, Rev.
TP-40, Rev.
"Seismic Structural Steel Inspection and Documentation System"
"Material Status Verification"
"HVAC Duct Weld Inspection and Documentation System"
"Training and Qualification of Construction Inspection Personnel"
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EBASCO Specification CAR-SH-BE-08
"Air Handling Units Safety Related Equipment Class B Seismic Category I" EBASCO-E-47-SH, ll/25/85 "Review of Vender Seismic 5 Environmental qualification Documentation for Safety Related Equipment" b.
The inspector reviewed samples of safety-related HVAC system records to determine whether the licensee was adequately preparing, reviewing, and maintaining a
system of quality records; whether there is reasonable assurance that the records reflect work accomplished consistent with NRC requirements and SAR commitments; and whether the records indicate any potentially generic problems, management control inadequacies, or other weaknesses that could have safety significance.
The following specific areas were examined.
(1)
The inspector reviewed the documentation for the HEPA filters and the Charcoal filter associated with E6 (1B-SB) air handling unit to verify conformance to the applicable portions of Regulatory Guide 1.52, Revision 2.
The filters were ordered to comply with ANSI/ASME-N509-1976 and the Charcoal was ordered to comply with ANSI/ASME-N509-1980.
The inspector had the following findings:
(a)
The certificate of compliance (COC) for the High Efficency Particulate Air (HEPA) filters listed several exceptions to the specification that have not been resolved by licensee.
This matter wi 11 be inspector followup item 50-400/86-29-02:
(b)
The COC for the HEPA filters does not include the identification of documents and test reports which support the COC as required by ANSI/ASME N509-1976, paragraph 5. 1.4.
Thi's matter will be identified as inspector followup item 50-400/86-29-03:
"Incomplete HEPA Filter Documentation."
(c)
The certification documentation for the activated charcoal does not include the results of the qualification test in accordance with ANSI N509 as required by paragraph 3.i. of Regulatory Guide 1.52, Revision 2.
This matter will be identified as inspector followup item 50-400/86-29-04:
"Activated Charcoal gualification Test Results."
(d)
The licensee was, at the time of this inspection, unable to provide objective quality evidence (0(E) to substantiate compliance with the last paragraph of Regulatory Guide 1.52, Rev.
2, Section 3.i.
This matter will be identified as Inspector followup item 50-400/86-29-05:
"Charcoal Filter Design Data."
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(e)
Using the figure of 31.5 lbs/cu.ft. for charcoal, provided by the licensee, and the cumulative weights listed on the receiving inspection reports for charcoal in Lot 44, Batch 10, (ll;629 lbs.) the batch volume would appear to be 369.1 cu.ft.
This appears to be contrary to third paragraph of Section 3.i. of Regulator Guide 1.52, Rev. 2, which limits batch volume to 350 cu. ft.
This matter will be identified as Unresolved Item 50-400/86-29-06:
"Charcoal Batch Volume."
'2)
The inspector reviewed the below listed nonconformance reports related to HVAC systems to determine whether the records are being properly identified, stored, and can be retrieved in a reasonable time; the records are legible, complete, and indicate that reports are promptly reviewed by qualified personnel for evaluation and disposition of the immediate problem as well as for generic implications and trending; the records adequately document current status of nonconformances or deviations and corrective action; and resolution of nonconformances demonstrates good engineering practice.
Nonconformance Re orts NCR 84-2045 NCR 84-1396 NCR 84-0290 NCR 84-1340 NCR 84-2279 NCR 85-0669 NCR 85-0873 NCR 85-0925 NCR 85-0926 NCR 85-1166 d.
The inspector reviewed the below listed audit reports concerning safety related supports and HVAC to determine whether the require audits have been performed in accordance with schedule and functional areas in established audit plans; audit findings have been reported in sufficient detail to permit a meaningful assessment by those respon-sible for corrective action, final disposition, and trending and; the licensee/contractor has taken proper and timely followup action on those matters in need of correction.
Audit Re orts QACS 85-1324 QACS 85-1939 QACS 85-2078 QACS 85-2307 QAA/XX81-85-03 QAA/81-32
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Within the areas examined, no violations or deviations were identified.
8.
Licensee Identified Items (10 CFR 50.55(e))
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(Closed)
400/CDR 83-104, Defective Welds on 480V Switchgear
On March 4, 1983, the licensee notified Region II of a 50.55(e)
item concerning vendor weld deficiencies in the transformer sections of seismically-designed class 1E and nonclass 1E switchgear (transformers lA1, 1CA2-SA, 1A3-SA, 1B1, 1B2-SB and 1B3-SB).
The final report was submitted on March 28, 1985.
b.
NRC IE Region II Report 50-400/85-22 indicated the following:
"Corrective actions required reinspection by the vendor and the licensee, repair of weld defects, correction to drawings/documentation, and engineering analyses to justify actions taken.
On review of corrective actions, the inspector questioned the justification for accepting several welds which were not reinspected due to being covered with an approximately 1/4 inch thick coating of shellac.
Cognizant licensee personnel informed the inspector that this issue would be addressed and a
supplement to - the final report transmitted to Region II.
An addendum to the final report was submitted on February 28, 1986.
The report has been reviewed and determined to be acceptable by IE. II.
The inspector held discussions with responsible licensee representa-tive, reviewed supporting documentation, and observed representative samples of work to verify that the corrective actions identified in the report have been completed.
(Closed)
Item 400/CDR 84-184:
"6000 Lb. Reducers
- Incorrect Material Markings and Thickness" (10 CFR 50.55(e))
On August 13, 1984, the licensee notified IE.II of a 50.55(e)
item concerning ANSI rating stamping and thickness deficiencies in four ASME Class I flow restrictors.
The final report submitted on December 13, 1984, dated December 14, 1984.
The report has been reviewed and determined to be acceptable by IE: II.
The inspector held discussions with responsible licensee representatives, reviewed supporting documentation, and observed representative samples of work to verify that the corrective actions identified in the report have been complete 'I it J
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(Closed)
Item 400/CDR 84-192:
"Containment Platform Steel Weld Deficiencies" (10 CFR 50.55(e))
On November 9, 1984, the Licensee notified IE: II of a 50.55(e)
item concerning containment platform steel weld deficiencies.
The final report was submitted on May 30, 1985.
The report has been reviewed and determined to be acceptable by IE. II.
The inspector held discussions with responsible licensee representatives, reviewed supporting documentation, and observed representative samples of work to verify that the corrective actions identified in the report have been completed.
9.
Inspector Followup Items a.
(Closed)
Item 50-400/86-05-02.
"Spent Fuel Storage Rack Assembly Support" This item concerns the fact that the design of and the installation pattern of the spent fuel storage rack assemblies had changed with respect to the spent fuel pool bottom and the spent fuel storage rack assembly embedded support plates.
This change resulted in some of the spent fuel storage rack assembly support feet resting on liner plate and not on the intended embedded support plates which caused deflection of the liner plate.
The condition is described in Field Change Request No. AS-10360.
This inspector reviewed FCR AS-10360 and has no further questions.
This matter is considered closed.
b.
(Closed)
Item 400/86-11-01:
"Positive Welder Identification" This matter concerns the licensee's undocumented program,to assure positive identification of welders during pre-employment and employment qualification testing as well as updating and renewal testing.
The licensee has, in Revision 16, Change 2 of MP-02, "gualification of Welders and Welder Operators" provided a
documented requirement for positive identification of welders as discussed above.
The inspector has no further questions.
This matter is close I If M
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