IR 05000325/1978032
| ML19256A745 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 11/29/1978 |
| From: | Conlon T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19256A746 | List: |
| References | |
| 50-325-78-32, NUDOCS 7901100022 | |
| Download: ML19256A745 (3) | |
Text
UNITED STATES sk* 880
- p 0g'o NUCLEAR REGULATORY COMMISSION
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REGION il 101 M ARIETT A ST R E ET. N.W.
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g ATLANTA, GEORGI A 30303
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Report No.: 50-325/78-32 Docket No.: 50-325 License No.: DPR-71 Category: C
.
Carolina Power and Light Company Licensee:
336 Fayetteville Street Raleigh, North Carolina 27602 Facility Name:
Brunswick 1 Inspection at:
Southport, North Carolina Inspection conducted: November 18, 1978 Inspector:
T. E. C n n O
f
I Reviewed y:
Date T. E. Conlon, Chief Engineering Support Section No. 2 Reactor Construction and Engineering Support Branch Inspection Summary 18, 1978 (Report No. 50-325/78-32)
Inspection on November Special announced inspection of the Ultrasonic Examination Areas Inspected:
of Jet-Pump Riser Safe-Ends. This inspection involved 13 inspector-hours on site by one NRC inspector.There were no items of noncompliance or deviation identified Results:
79011oo ong
,
RII Rpt. No. 50-325/78-32-1-
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DETAILS Prepared b
/ Date T. I. Conlon, Chief Engineering Support Section No. 2 Reactor Construction and Engineering Support Branch Dates of Inspec n:
ovember 18, 1978
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Reviewed
/Dat6 T. E. Conlon, Chief Engineering Support Section No. 2 Reactor Construction and Engineering Support Branch 1.
Persons Contacted Carolina Power and Light (CP&L)
a.
- W. Tucker, Superintendent Technical and Administration
- W. Pearce, Project Coordinator R. White, Site QA Technician A. Bishop, Engineer BSER b.
Contractor Organization Lambert, MacGill and Thomas (LMT)
- T. Lambert, Level III Inspector / Supervisor
- Denotes those present at exit interview.
2.
Scope Special announced inspection to observe the reexamination, by ultra-sonic testing, of Unit I recirculation nozzle safe ends "D",
"E", "J" and "K" as stated in CP&L letter dated October 27, 1978 and NRC Isunediate Action Letter of October 2,1978.
Recirculation Nozzle Safe End Examination, (Unit 1)
3.
This reexamination was conducted in order to determine if the previously identified indications had undergone any change in size.
The location and magnitude (7 of DAC) of the previously identified indicati~ns for nozzle safe ends D, E, J and K are documented on Attachment 2 of the CP&L report, entitled " Reactor Circulation Safe End NDE Inspection Program" dated October 5, 197.
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RII Rpt. No. 50-325/78-32-2-The reexamination (UT) was conducted by the same contractor (LMT) using the same supervision, equipment, procedures and calibration standards as was used on the initial inspection done in September, 1978.
The result of this examination is documented on recorder tape as was the initial examination.
Recording the UT signal responses on tape allowed the contractor (LMT) to make an accurate comparison between the initial examination and this reexamination. The results of this comparison, as stated by the contractor (LMT), indicated no detectable change in the indications during the interim between September 27, 1978 and November 18, 1978.
4.
Exit Interview The NRC inspector did not conduct an exit interview because the individuals denoted in paragraph I were present during the entire evaluation and comparison of the UT data by the contractor.
However, the NRC inspector did request that the licensee evi,uate the possible loss or masking of signal response strength (for the identified indications) due to the recirculation system being full of water.
This request was made by phone to the plant manager on November 20, 1978.
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