IR 05000400/1982002
| ML20050A608 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 02/09/1982 |
| From: | Burger C, Maxwell G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20050A594 | List: |
| References | |
| 50-400-82-02, 50-400-82-2, 50-401-82-02, 50-401-82-2, NUDOCS 8204010485 | |
| Download: ML20050A608 (6) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION
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E REGION 11
101 MARIETTA ST., N.W., SUITE 3100
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ATLANTA, GEORGIA 30303
Report Nos. 50-400/82-02 and 50-401/82-02 Licensee: Carolina Power and Light Company 411 Fayetteville Street Raleigh, NC 27602 Facility Name: Shearon Harris Docket Nos. 50-400 and 50-401 License Nos. CPPR-158 and CPPR-159 Inspection at Shearon Harris site near Raleigh, North Carolina Inspector:
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G. F. flaiwal (/
' Date Signed Approved by: br W##
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C. Burger, Segyfon Chief, Division of date/ Signed Resident antf Reactor Project Inspection SUtif1ARY Inspection on December 20, 1981 - January 20, 1982 Areas Inspected This routine inspection involved 76 resident inspector-hours on site in the areas of concrete (Unit 2), equipment storage (Unit 1&2); protection of safety-related equipment (Unit 1), installation of safety-related components (Unit 1) and welding activities.
Results Of the five areas inspected, no violations or deviations were identified in four areas; one violation was found in one area (Violation - failure to protect equipment from the environmental and adjacent construction activities - see paragraph 7).
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0204010485 820323 PDR ADOCK 05000400 G
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L DETAILS 1.
Persons Contacted
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Licensee Dnployees
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- R. M. Parsons, Site Manager
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- H. J. Chiangi, Manager, Engineering and Construction QA/QC
- G. M..Simpson, Principal Construction Inspection Specialist
- G. L. Forehand, Director QA/QC
- A. M. Lucas, Senior Resident Engineer
- R. Hanford,' Principal Engineer, Welding
- D. C. Whitehead, Senior QA Specialist
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- E. E. Willett, Resident Engineer, Mechanical
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- T. Wait, QA/QC Specialist NRC j
- J. L. Coley, USNRC-RII
- J. W. York, USNRC-RII
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on January 21, and 22, 1982, with those persons indicated in paragraph 1 above.
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Licensee Action on Previous Inspection Findings Not inspected.
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Unresolved Items Unresolved items are matters about which more information is required to
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determine whether they are acceptable or may involve violations or devia--
tions. -New unresolved items identified during this inspection are discussed l
in paragraph 8.b.(1).
5.
Concrete - Unit 2 c.
_The inspector observed portions of a concrete placement being made in~
the Unit 2 reactor auxiliary building (pour numbered 2RASL236008). The above observations included:
(1)
Inspecting the installed conditions of the concrete forms, i.e.
cleanliness, level and tightness t
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(2) Placement activities as they relate to delivery time, mixer revolution counter, rate of rise, free fall, testing of the concrete at the point of delivery and consolidation (3) The presence of construction inspection personnel to assure compliance with construction specifications and procedures (4) Suitable protection for tesc cylinders from adjacent activities
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(5) Suitable curing of placed concrete b.
The inspector observed that the minimum curing temperature for the above placed concrete had not been maintained for a short period of time. The responsible site inspection personnel documented the nonconforming condition on discrepancy report DR-C-1409.
The following were referenced riuring the above observations:
PSAR section 1.4; design specificatica CAR-SH-CH-6, construction procedures WP-04, WP-05, CQA-6, TP-15 and TP-17.
No violations or deviations were identified in the areas inspected.
6.
Storage of Major Components - Units 1 and 2 a.
The inspector observed the stored condition of the reactor vessels for Units 1 and 2.
The storage conditions were evaluated to determine whether requirements are being met as follows:
(1) Storage in accordance with approved procedures (2) Seals and devices identifying vessel internals' atmospheric conditions (3) Condition of protective coating and/or covering (4) Dunnage or supports prevent entry of dirt, water or flooding (5) Supports have adequate strength 'o prevent shifting or collapse of the structure b.
The inspector observed the stored condition of the safety injection accumulators for Unit 2, the Unit 2 steam generators and the residual heat removal heat exchangers identified as 2168-48, 183, 4D, 4E, 188, 186, and 1B7. Their storage conditions were evaluated to determine whether requirements are being met as follows:
(1) Storage in accordence with approved procedures (2) Purged with protective gas to prevent corrosion (3) Dunnage or supports to prevent entry of dirt, water or flooding
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During the above evaluations the following were referred to for requirements: PSAR section 1.4; constructior. procedures WP-106, AP-XIII-05, PGD-002, and AP-XIII-07.
No violations or deviations were identified in the areas inspected.
7.
Protection of Safety-Related Equipment - Unit 1 a.
As a result of observations made on December 15 and 18,1981, and subsequent follow-up the following were noted.
(1) An unidentified liquid, later found to be concrete curing water dripping from a concrete placement on a floor above was dripping on and into loop "A" reactor coolant pump casing. The inspector discussed the unsatisfactory condition, which was observed on December 15, 1981, with the responsible QA personnel who initiated'
a nonconformance report (NCR-M-156).
(2) On December 18, 1981 and during subsequent tours of the reactor auxiliary building, south end at about elevation 289', the inspector observed and informed the responsible CP&L management personnel of the following unsatisfactory conditions related to class 1E switchgear 1A-SA:
(a) The switchgear was found partially uncovered and unprotected from adjacent construction activities (welding and grinding).
(b).
The switchgear was found to be covered in part with a material which supports combustion. There was paper and debris in several cubicles of the switchgear.
(c) The top of the emergency service water pump 1ASA auxiliary cabinet was damaged.
The inspector was informed that the damage resulted from a piece of structural steel falling against the top edge of the switchgear.
The inspector discussed the above unsatisfactory conditions with the CP&L Project flanager who required immediate corrective action in covering the switchgear with a material which would protect it from the adjacent welding and grinding activities. The other unsatisfactory conditions were documented by the responsible CP&L QA personnel on nonconformance report NCR-E-034.
b.
On January 11, 1982, the inspector observed a feedwater valve, serial number 56805, lying on the concrete slab just outside Unit 1 main steam / main feed water containment penetration. The valve was partially covered allowing no protection to the valve end, which was not capped.
As a result, water had accumulated inside the valve on the seating surface and had frozen. The ambient temperature around the valve was about 4 F.
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The inspector brought the above unsatisfactory conditions to the attention of responsible CP&L QA personnel and as a result a noncon-formance report was written (DDR-778).
The inspector informed the CP&L management personnel that failure to protect safety-related equipment from the environment and adjacent construction activities is contrary to 10 CFR 50, Appendix B, Criterion
XIII as implemented by PSAR section 1.8.5.13; CP&L Corporate QA Program, section 5.4.1.f and construction procedures AP-XIII-07-PGD-002 l
and WP-106, section 4.8.
This is a violation " Failure to protect equipment from the environment and adjacent construction activities"
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(400/82-02-01).
Except as noted, no other violations or deviations were identified in the areas inspected.
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Installation of Safety-Related Components - Unit 1 a.
The inspector interviewed the CP&L construction inspection and mechanical groups responsible for the installation of loop "A" reactor coolant pump casing. The installation was inspected to determine whether requirements are being met as follows:
(1)
Installation specifications (2) Placement and alignment (3) fiounting and supporting (4)
Inspection (5)
Identification of nonconforming conditions (6) fiaterial identification and use b.
As a result of the above inspections the following were detennined:
(1) The site document control records were evaluated and found not to contain sufficient infonnation to determine whether the materials utilized during the manufacturing of the support columns (tubular members) meet the installation drawing and specification
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requirements -(drawing 1364-2127 revision 7 and specification G-952628). The discrepancy was documented on nonconformance report numbered DDR-784 and will be further evaluated during the next reporting period.
This matter is unresolved.
(400/82-02-02)
(2) The temporary adjustment bolts (jacking bolts) for the steam generators and reactor coolant pumps
"A", "B" and "C" were found not to be installed as prescribed on the installation drawing 1364-2127 revision 7.
Several of the bolts were not installed and several were installed backwards.
The inspector discussed this
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concern with RII supervision, site CP&L management and Westing-house personnel.
As a result, a pemanent waiver (PW-H-475) was written to document what action will be utilized in place of the jacking bolts. The inspector has no further questions about this matter at this time.
(3) The clevis pin cotter bolts for loop "A" reactor coolant pump casing support column were found to be only finger tight. This condition and the conditions noted in 8.b.(1) and (2) above were documented by construction inspection personnel on nonconformance reports numbered DR-M-232, 233 and 234.
c.
The inspection status of the installation of loop "A" reactor coolant pump casing has not completed phase I inspection, as described in construction procedure TP-28.
However, the inspector was infonned that as of this reporting period approximately twelve nonconformance reports (DRs and DDRs) have been written concerning the installation of the reactor coolant pump casings. The nonconformances vary in nature, i.e.
construction inspection missing inspection hold points, missing hardware (lock nuts, jam nuts, nuts, and washers) and those items listed in 8.b.(1), (2) and (3) above.
During the above observations the following were referenced for require-ments:
PSAR section 1.4; construction procedures WP-131, TP-28, WP-105; Westinghouse drawing 1364-2127 revision 7 and specification G-952628.
No violations or deviations were identified in the areas inspected.
9.
Other Areas The inspector participated in an investigation involving site welding activities. The results of the investigation will be documented in subsequent RII inspection reports.
No violations or deviations were identified in the areas inspected.
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