IR 05000369/1978033
| ML19294A543 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 11/03/1978 |
| From: | Dyer J, Martin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19294A542 | List: |
| References | |
| 50-369-78-33, NUDOCS 7812070315 | |
| Download: ML19294A543 (4) | |
Text
.
UNITED sT ATEs
[p* 880 jo, NUCLEAR REGULATORY COMMISSION 0g
'
!~
%
REGION il 101 M ARIETT A STREET. N.W.
I c
[
ATLANT A, GE ORGI A 3C3o3
o
%....*/
Report No.-
50-369/78-33 Docket No.-
50-369 License No -
CPPR-83 Licensee:
Duke Power Company Post Office Box 2178 422 South Church Street Charlotte, North Carolina 28242 Facility Name:
McGuire Nuclear Station Inspection at:
McGuire Unit No. 1 Inspection Conducted:
October 3-5, 1978 Inspector:
J. A. Dye
[
,
Reviewed by:
[
//
R. D. Martin, Chief p'atf Nuclear Support Section No. 1 Reactor Operations and Nuclear Support Branch Inspection Sumary Inspection on October 3-5, 1978 Report No. 50-369/78-33 Areas Inspected: Routine unannounced inspection related to preoperational test procedure review, hot functional testing planning and scheduling and a tour of plant areas.
The inspection involved 21 inspector hours onsite by one NRC inspector.
Results:
Vithin the areas inspected, no items of noncompliance or deviations were identified.
781207c315-
.
,
RII Rpt. No. 50-369/78-33 I-I DETAILS I Prepared by: W.
Afs
//
[73 d. A. Dyer,jReactor Inspector Date Nuclear Support Section No. 1 Reactor Operations and Nuclear Support Branch Dates of Inspection: October 3-5, 1978 Reviewed by:
// h///m f//g/9p R. D. Martin, Chief Jfat4 Nuclear Support Section No. 1 Reactor Operations and Nuclear Support Branch 1.
Persons Contact-d Duke Power Coispany E. Estep, Associate Engineer G. Galbreath, Assistant Engineer M. Kitlan, Assistant Engineer D. McCarty, Assistant Engineer
- M. McIntosh, Plant Manager M. Pacetti, Test Engineer J. Rowe, Junior Engineer
- M. Sample, Technical Services Engineer
- L. Weaver, Performance Engineer R. White, Assistant Engineer
- Denotes those present at the exit interview.
2.
Licensee Action on Previous Inspection Findings Not applicable.
3.
Unresolved Items None.
4.
Exit Interview The inspector met with licensee representatives (denoted in paragraph 1)
at the conclusion of the inspection on October 5, 1978. The inspector summarized the purpose and findings of the inspection as reported in the following paragraphs.
. _. _ _. - _
.
,
RII Rpt. No. 50-369/78-33 I-2 5.
Review of Preoperational Test Procedures Preoperational test procedures were reviewed for conformance to Regulatory Guide 1.68, McGuire Station Directives 3.2.2 and 4.2.1, FSAR Table 14.1.3-1, and FSAR Sections 3.9.1, 7.4.1.1, 7.4.1.2, 7.4.1.3, 7.4.1.4, 7.4.1.6, 9.2.2, 9.2.4, 9.3.4, and 10.4.7.2.2.
The
" Procedure Major Change Process Record" was also reviewed for those procedures which had been approved.
No deficiencies were noted during review of the following procedures:
TP-1-A-1200-1, Component Cooling Functional Test - Approved a.
October 11, 1977.
b.
TP-1-A-1200-05A, NV Functional Test (Cold) - Approved June 9, 1978.
c.
TP-1-A-1200-05B, NV Functional Test (Hot) - Draft Procedure.
d.
TP-1-A-1200-13, Boric Acid System Functional Test - Approved August 29, 1978.
e.
TP-1-A-1250-04, Auxilary Feedwater System Functional Test -
Approved September 8, 1978.
f.
TP-1-A-1400-01, Nuclear Service Water System Functional Test-Approved February 6, 1978.
g.
TP-1-A-1400-10, Nuclear Service Water Suetica Verification for Auxilary Feed Pumps - Approved May 8,1978.
6.
Hot Functional Testing a.
Hot functional testing (FFT) is presently scheduled to commence November 1, 1978. The EFT schedule lists 23 tests to be conducted.
The current status of the tests is as follows; 11 tests have been approved, 10 are in draft form, and 2 are being written.
The inspector, again, emphasized the need for procedures to be made available to the NRC in sufficient time for their review prior to their intended use.
A licensee management representative stated that normally the procedures would have been made available to the NRC in sufficient time for review. He said that HFT was moved ahead in the test program due to the fact that the
" Integrated Leak Rate Test" would be delayed due to valve problems.
b.
The inspector noted that there was no test identified in the test procedure index to cover pre and post HFT examination of the core support structures for integrity per Regulatory Guide 1.20 and identified in FSAR Figure 3.9.1-1.
A licensee management repre-sentative stated that the pre EFT insrcetion was performed under the construction department.
He also aated that the post HFr
,
inspection would be performed under cognizance of the steam production department (Operations) and that a procedure would be
.
.
RII Rpt. No. 50-369/78-33 I-3 written and approved to cover the inspection. The writing and approval of a procedure for post HFT inspection of the reactor internals is designated as outstanding item 78-33-01.
7.
Previously Identified Areas of Concern a.
IE Report 50-369/78-06 Detail I.5.b.6 concerned verification that all non-essential diesel trips were bypassed during an emergency start. The inspector reviewed PT-1-A-1350-08, approved August 22, 1978, and confirmed that the test verifies that the fo11-ving non-essential diesel trips are bypassed during an emergency start:
1)
Lube oil temperature.
2)
Jacket water temperatures.
3)
Jacket water level.
4)
Jacket water pressure.
5)
Crankcase pressure.
6)
Manual stop (local and remote).
7)
Halon fire protection.
The bypassing of the generator breaker instantaneous overcurrent trips during an emergency start is being verified in conjunction with the station blackout test.
This item is now closed.
b.
IE Report 50-369/78-16 Detail I.5.b. concerned verification that opening times for those valves that receive a Sp signal be performed under maximum expected differential pressure conditions.
The inspector reviewed a portion of the test results for test TP-1-A-1200-04 and confirmed that the opening times were verified as required. This item is now closed.
c.
IE Report 50-369/78-21 Detail I.6. erpressed the inspector's concern about condensate f rom service water lines dripping on the steam driven auxilary feed pump control panel and the auxilary shutdown panel.
The inspector verified by visual observation that insulation had been installed to prevent condensation.
This item is now closed.
8.
Facility Tour The inspector conducted a tour of the reactor building, auxilary building, turbine hall and control room to determine construction status as related to HFT and to observe housekeeping practices. No discrepancies were identified.