IR 05000373/1982013
| ML20054B545 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 03/31/1982 |
| From: | Choules N, Chrissotimas N, Chrissotimos N, Gardner R, Gwyn T, Mendez R, Norton J, Reyes L, Walker R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20054B535 | List: |
| References | |
| 50-373-82-13, NUDOCS 8204160585 | |
| Download: ML20054B545 (9) | |
Text
.
-
-
.
.
.
U.S. NUCLEAR REGULATORY COMMISSION
REGION III
Report No. 50-373/82-13(DPRP)
Docket No. 50-373 License No. CPPR-99 Licensee: Commonwealth Edison Company Post Office Box 767 Chicago, IL 60690 Facility Name: LaSalle County Nuclear Station, Unit 1 Inspection At: LaSalle Site, Marseilles, IL Inspection Conducted: March 15-19 and 22-26, 1982
[
}l3/f/ %
Inspectors:
L. A. Reyes U/
N. C E6les
/
l'
}f3tff N. Chrissotimos
-
T. P.
n
..
tL h *
W R. N.
ardner 3/3/f8t'
.
'
,
G/3/ /Q j
%.Mendez R
!
l y%
U. Norton 3/3//82.
$C 3 "7b b Approved By:
R. D. Walker, Chief Reactor Projects Section 1C
'
.
I 8204160585 820401 PDR ADOCK 05000 G
- - _ _. --
- - - - - - --._-
__
_ - _ _,
__.
.__
_ _
__
k
.
.
Inspection Summary Inspection on March 15-19 and 22-26, 1982 (Report No. 50-373/82-13(DPRP))
Areas Inspected: Routine, resident inspection, preoperational testing and management meeting. The inspection consisted of a follow up on previous in-spection findings, 10 CFR 50.55(e) reports, fire protection review, follow up on allegations, interpretation of Associated Piping and Engineering (APE)
shop radiographs and management meeting held on March 19, 1982. The inspec-tion involved a total of 225 inspector-hours onsite by seven NRC inspectors including 26 inspector-hours onsite during off-shifts.
Results: Of the four areas inspected, no items of noncompliance or deviations were identified.
.
&
j Y
!
.
I
._
_
__.
._
.
. -
-
-.
_ _ _ _ _ _ _ _. _ _ _.
_
_
_ _. - - _
.
s DETAILS 1.
Persons Contacted B. B. Stephenson, LaSalle County Station Project Manager a, b R. H. Holyoak, Station Superintendent a R. D. Kyrouac, Quality Assurance Engineer a G. J. Diederich, Station Operating Assistant Superintendent R. D. Bishop, Administrative & Support Services Assistant Superintendent a, b R. Raguse, Senior Operating Engineer J. M. Marshall, Operating Engineer W. Huntington, Assistant Technical Staff Supervisor H. J. Hentschel, Assistant Technical Staff Supervisor F. Lawless, Rad-Chem Supervisor E. E. Spitzner, Startup Coordinator E. Stevak, Quality Assurance L. W. Duchek, Project Management Staff J. Bowers, Onsite Nuclear Safety Engineering Group (ONSEG)
.
T. Borzym, Security Administrator l
J. J. Maley, Manager of Projects b T. E. Quaka, Site Quality Assurance Superintendent a J. J. O'Connor, President b C. Reed, Vice President b T. E. Watts, Project Engineer
J. W. Gieseker, Assistant to Site Construction Superintendent D. L. Shamblin, Staff Assistant Project Manager's Office a B. R. Shelton, Project Engineering Manager b L. O. De1 George, Director of Nuclear Licensing b D. Skoza, Project CDE c E. Weldorf, Project CDE c R. Vine, QA Engineer c The inspector also interviewed other licensee employees including members of the technical, operating, and construction staff, as well as certain licensee contractor employees.
a.
Denotes persons present at management interview conducted at the close of the inspection period.
b.
Donotes persons present at the Management Meeting held in the Region III office on March 19, 1982.
,
c.
Denotes persons at the exit interview conducted on March 24, 1982.
2.
Follow Up On Previous Inspection Findings (Closed) Unresolved Item (50-373/81-26-02): The licensee's cable termination procedure did not include torque requirements for bolted connections. The licensee performed tests in December 1981 and January 1982, to determine if the current method of tightening
.__
.
_
..
_.
-.
_ _ _.
.
bolted connections results in an adequate connection. The test results indicate that the licensee's method is acceptable.
(Closed) Unresolved Item (50-373/82-11-05): The inspector requested the licensee to provide an evaluation of the effects of onsite modi-fications on the seismic qualification of Electrical Protective Assemblies. The Component Qualification Division of Sargent and Lundy analyzed the as-built mounting of the assemblies and determined that the as-built mounting is adequate for both OBE and SSE conditions.
It was further determined that the as-built mounting does not affect the original seismic qualification report.
(Closed) Unresolved Item (50-373/81-26-01): Color coded tags had not been installed, as required, on instrument sensing lines. The licensee has received marked up Piping and Instrumentation Drawings (P&ID's)
from Sargent and Lundy. h ese P&ID's identify both the instrument lines which require tagging and the color of the tags to be installed.
Sargent and Lundy, in a letter dated March 12, 1982, has approved the use of Brady B-361B low halid tape in lieu of the metal tags specified in Specification J-2530.
The inspector reviewed several instrument lines and determined that they were identified in accordance with the P&ID's.
(Closed) Open Item (50-373/82-11-02): The licensee was requested to obtain additional data concerning the overload devices installed in Klockner-Moeller Motor Control Centers (MCC). The inspector reviewed the letter received by the licensee from Klockner-Moeller on March 25, 1982. The letter stated that the method used in terminating internal wiring to the MCC overloads was acceptable.
(Closed) Open Items (373/79-33-03), (373/81-30-01) and (373/81-36-01):
Closure of IE Circulars No. 79-04, No. 81-09 and No. 81-13.
The inspector determined for each of these circulars that:
a.
The circular was received by licensee management.
b.
That a review for applicability was performed.
c.
For circulars that were applicable to the facility, appropriate corrective actions have been taken or are scheduled to be taken.
(Closed) Open Item (373/81-06-12): FSAR discussion of RHR Safety Design Bases. Amendment 59 to the FSAR includes a revision to Section 5.4.7.1 which clarifies the safety related modes of RHR.
(Closed) Open Item (373/81-00-124):
Locking mechanism on shielding doors. The inspector conducted a tour of the Unit I reactor building and verified that doors 418, 394, 395, 374, 225, 226 have a locking mechanism installed.
_
.
(Closed) Unresolved Items (373/80-16-03), (373/80-30-03) and (373/79-38-20): Closure of IE Bulletins No. 80-11, No. 80-17, and No. 79-02.
The inspector determined that for each IE Bulletin sent to the licensee for action, the following actions taken by the licensee met bulletin requirements and licensee commitments:
a.
The written response includes the required information.
b.
The written response includes adequate corrective action com-mitments based on information presented in the bulletin and licensee's response, c.
The licensee management forwarded copies of the written response to appropriate onsite management representatives.
d.
The information discussed in the licensee's written response was accurate.
e.
The corrective action taken by the licensee was as described in the written response.
The inspector determined that for each bulletin sent to the licensee for information, the following actions were taken by the licensee.
a.
The bulletin was received by licensee management.
b.
A review for applicability was performed.
c.
For bulletins applicable to the facility, appropriate corrective actions have been taken or scheduled to be taken.
3.
10 CFR 50.55(e) Reportable Items (Closed) 10 CFR 50.55(e) Reportable Item (373/81-xx-01): The voltage rating of certain motor terminal blocks in installed limitorque valves was less than allowed by specifications. The final report on this deficiency was received by the Region III office on March 25, 1982.
This letter stated, in part, that all Unit 1 limitorque valves have been inspected and that all affected safety related valves have had the motor terminal blocks removed and a lug to lug connection installed.
The lug to lug connections were inspected by Foley Quality Control personnel. The inspector reviewed the quality records for seven limitorque valve motor connections. The records were retrievable and acceptable. The inspector observed the lug to lug motor connec-tions for four limitorque valves. The connections were acceptable.
Nonconformance Report 488 which tracked this item was closed on March 25, 1982.
No items of noncompliance or deviations were identified.
.
_
.-
.. - _
- -
_. -
_ _ - _ - _ -.
. _ -
_.
.
.
4.
Review of Preoperational Test Program System Test Deficiencies The inspectors reviewed the System Test Deficiencies for the following Preoperational Tests / System Demonstrations:
SD-FC-101
" Fuel Pool Cooling Filter Demineralizers" PT-MS-101B
"MSIV and Main Steam Instrumentation" PT-NR-101A
" Source Range Moniter" PT-NR-101B
" Intermediate Range Monitors" PT-NR-101C
" Power Range Monitors" PT-VJ-101
" Machine Shop HVAC"
PT-VO-101
"Off Gas Filter Building HVAC"
'
PT-D0-201
" Unit No. 2 Diesel Oil System" PT-FC-101
" Fuel Pool Cooling" The inspectors reviewed all of the open deficiencies in these system tests to assure that they are properly categorized. The inspectors
also reviewed a sample of the closed deficiencies to assure that they have been properly closed.
The inspectors determined that the open deficiencies in these system
!
tests are being properly classified and that the licensee is correctly i
closing deficiencies found during the Preoperational Test Program.
This review closes the following NRC Region III inspection report open items:
>
(373/81-20-14); (373/81-18-01); (373/81-18-02); (373/81-18-03);
(373/81-18-04); (373/81-18-05); (373/81-43-05); (373/81-28-17);
and (373/82-10-09)
No items of noncompliance were identified in this area.
5.
Fire Protection Review i
The inspector examined the licensee's commitments to the Fire Protection Safety Evaluation Report (FPSER) during March 17-19, 1982 and March 24-26, 1982. The inspector identified the following three areas of concern:
1.
Sections 9.5.6.2 and 9.5.6.3 requires the licensee to provide three hour fire rated dampers.
Fire dampers in the auxiliary equipment room and the Division II switchgear room do not all contain the required three hour fire rating. The licensee stated they have issued deficiency reports and will respond to this item at a later time.
(373/82-13-01A)
2.
Section 9.5.6.6 of the FPSER requires a 50' separation for redundant cabic divisions at the 731' elevation outside the Unit 1 drywell. The inspector noticed that the redundant I
divisions were wrapped with a fire proofing material but were not separated by the required 50 feet.
(373/82-13-01B)
l
L
-. _._ -_
-
- _ _ _,_
-_.
____
___
________
_
__
_
_
.
The licensee stated they are asking for an exemption from NRR.
No items of noncompliance or deviations were identified.
6.
Interpretation of Associated Piping and Engineering (APE) Shop Radiographs The inspector reviewed radiographs of the following welds that were radiographed by Associated Piping and Engineering Corporation (AP&E) or the Youngstown Welding and Engineering Company (YW&E), fabricated by AP&E, supplied to GE who supplied the material to CECO for replacement spools in the recirculation loop, Units 1 and 2.
Safe ends that were radiographed by AP&E were also reviewed. The following radiographs were interpreted to determine:
a.
That the required T holes are visible and discernible.
b.
That the T holes have not been enhanced or altered.
!
c.
That the radiographs are in accordance with ASME Section III, 1974 Edition, Winter 1974 Addenda for the spools and in accordance with ASME Section III, 1974 Edition, Summer 1976 Addenda for the safe ends.
d.
That the reports are complete and acceptable.
Piece MarkNo.
Shop Sheet No.
Weld No.
17 Long Seam 0.625" 2/77 YW&E ELBOW 9
A&B 0.750" 3/77 AP&E G012-30-A-19
W-A 0.575" 9/77 AP&E G012-30-A-19
B 0.525" 8/77 AP&E
17 Long Seam 0.625" 3/77 YW&E G012-150-A-20
W-B & W-A 0.575 2/78 AP&E G012-150-A-20
ELLA & B 0.750" 4/77 AP&E G012-150- A-19
B 0.525" 8/77 AP&E G012-150-A-19
A 0.525" 9/77 AP&E
,
'
G012-240-B-20
TUBE 7A 0.575" 1/20/78 AP&E G012-240-B-20
W-A & W-B 0.575" 2/13/78 AP&E GE112D2542P1
W-A 2.750" 1/9/79 AP&E GE112D2542P1
W-A 2.750" 1/12/79 AP&E Safe End G012-210-B-19
B 0.575" 8/22/77 AP&E ELBOW 13
A&B 0.750" 3/31/77 AP&E 19B
Long Seam 0.625" 7/11/77 YW&E GE112D2547P1
W-A 2.750" 1/15/79 AP&E Safe End CE112D2547P1
W-A 2.750" 1/12/79 AP&E Safe End l
G012-120-A-19
W-A 0.575" 9/24/77 AP&E I
G012-60-A-19
A 0.575" 9/23/77 AP&E G011-B-20
Long Seam 0.625" 2/28/77 YW&E I
I
. _ _
_
- -.
_ _
..
- -
.-
.. - -
-.
-
..
-
-
_
-
. -.
.
.
..
Piece MarkNo.
Shop Sheet No.
Wold No.
Thickness Date RT Co RT G011-B-20
TUBE 30A 0.575" 1/23/78 AP&E G012-33-D-20
Long Seam 0.625" 7/11/77 YW&E G012-A-20
Long Seam 0.625" 2/25/77 YW&E 112D2706P006
W-A & W-B 0.575" 2/10/80 YW&E 112D2706P004
W-A & W-B 0.575" 2/5/80 AP&E The above welds are approximately 25% of the GE supplied welds on site.
CECO has reviewed all radiographs supplied from GE except safe ends and they are to be reviewed by CECO.
,
No items of noncompliance or deviations were identified.
7.
Exit Interview The inspector met with site representatives (denoted in Persons Contacted
,
Paragraph) at the conclusion of the inspection. The inspector summarized l
the scope and findings of the inspection noted in this report.
8.
Management Meeting Held in NRC Region III Office on March 19, 1982 a.
Attendance CECO Those denoted in Paragraph 1.
NRC J. G. Keppler, Regional Administrator R. L. Spessard, Director, Division of Project and Resident Programs C. Norelius, Director, Division of Engineering and Technical Inspection R. C. Knop, Chief, Reactor Projects Branch 1 R. D. Walker, Chief, Projects Section 1C J. Creed, Chief, SafeguardsSection I. N. Jackiw, Chief, Test Programs Section
,
N. Chrissotimos, Senior Resident Inspector
'
L. A. Reyes, Senior Resident Inspector i
b.
Meeting Summary This meeting was held between Commonwealth Edison Company (CECO) and NRC Region III representatives to review the sub-stantive issues that are germane to the NRC Region III review i
with respect to license issuance. The issues identified were
)
as follows:
(1) Fuel load date variance from the March 15, 1982, fuel load date reported to NRR. CECO stated that they expect to be ready to load fuel by April 15, 1982. NRC Region III took the position that May 1, 1982, fuel load date was more realistic.
!
I l
.-. _
_
-
_ _ _
...
_
_ _. _ _ _ _. _ _ _. _
..
(2) System Deficiencies. The current status of deficiencies was addressed by both CECO and NRC Region III.
NRC Region III requested a weekly update on the status of deficiencies and noted that prior to issuance of a license all deficiencies must be categorized as to their impact to fuel load and initial criticality.
NRC Region III requested CECO support in the retrieval of documentation pertaining to the review of deficiencies.
NRC Region III indicated that they will notify CECO of the time and open items inspectors will be reviewing in order to improve the efficiency of the review.
NRC Region III will prepare a weekly inspection report to promptly document the review status of open items.
(3) Security Program. NRC Region III requested CECO to conduct an audit of the functional status of the Security Program.
NRC Region III suggested the audit be conducted by CECO Corporate and knowledgeable security personnel from other operating nuclear power stations in the c0mpany.
During the meeting, it was agreed that another meeting would be held to discuss progress on these issues in approximately two weeks.
L