ML19332A155
| ML19332A155 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/11/1980 |
| From: | Chaudhary S, Ebneter S, Mcbrearty R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19332A154 | List: |
| References | |
| 50-289-80-13, IEB-79-02, IEB-79-2, NUDOCS 8009100899 | |
| Download: ML19332A155 (8) | |
See also: IR 05000289/1980013
Text
.
.
.
.
U.S. NUCLEAR REGULATORY COMMISSION
O
0FFICE OF INSPECTION AND ENFORCEMENT
-
U
Region I
Report No.
50-289/80-13
Docket No.
50-289
Licensa No.
Priority
Category
C
--
Licensee:
Metropolitan Edison Company
P.O. Box 542
Reading, Pennsylvania
Facility Name:
Three Mile Island, Unit 1
Investigation at: Middletown, Pennsylvania
Investigation conducted:
May 9 - June 19, 1980
ca D a*/
-
7!9!80
Investigators;
s
~
L. Gage, Reactof Inspector
date signed
Y ls. n N 1 w& L --
7h 80
S. Chaudnary, Rfactor Inspector
'date signed
$'$.k' Y
h
9 /999
R. McBrearty, Reactg'r Inspector
te ' signed
S. Ebneter
S. Ebneter Chief, ESS #2, RC&ES Branch
date signed
~
7 [f/ ffd
Approved by:
t
S. Etineter, Chief, Engineering Support
date signed
Section #2, RC&ES Branch
Investigation Sumary:
Inspection on May 9-June 19,1980 (Report No. 50-289/80-13)
Areas Inspected:
Routine, unannounced inspection by regional-based inspectors
of work activities and records associated with the Unit 1 Restart Program,
including: licensee response to I.E.Bulletin 79-02, high-pressure injection
cross-connect modification (task RM-14), and identification of safety-related
systems and components. The inspection involved 96 inspection hours on site by
three NRC regional-based inspectors and one Section Chief.
Results:
No item of noncompliance was identified.
--
L
8009100 N 7
i
Region I Fonn 143
(Rev. October 1977)
'
.
-
.
.
.
_-
- , - _
_ _ _ _ _ . _
_ _ _
_ _ _ _
.
.
DETAILS
1.
Persons Contacted
GPUSC
J. Becker, Level III Examiner
D. Jones, Quality Centrol Inspector
N. Kazanas, Managar of Quality Assurance
R. Prabhakar, Supervisor, Generation QA Engineering
J. Wright, Quality Control Manager
L. Zubey, Construction Manager
Metropolitan Edison Company
G. Miller, Unit 1 Director, Restart
M. Shaffer, Start-up and Test
- G. Troffer, Deputy Restart Manager
Catalytic, Inc.
R. Paterson, Welding Engineer
U.S. Nuclear Regulatory Commission
A. Fasano, Chief, Site Operations Section, TMI
- D. Havercamp, TMI-1, Senior Resident Inspector
- Denotes personnel present at exit interview.
2.
Listing of Safety-Related Systems and Components
The inspector asked the licensee for the status of the listing of safety-
related equipment, referred to by the licensee as the "QCL List." This
list is to supersede the listing of safety-related equipment contained in
licensee procedure GP-1008, Revision 2.
The licensee had earlier stated
that the QCL List would be published on May 22, 1980 (refer to paragraph 9,
I.E. Report No. 50-289/80-09). The licensee stated that the QCL List was
being reviewed by their Engineering Deparbaent and was not in final form.
I
^
!
,
- _ - . -.
.
_.
.
- _ _ _ _ - _ _ _ _ _ _ _ _ _
__ _ __ -_-_____-______
.
.
3
.
The inspector asked the licensee for the basis on which he was presently
designating engineering change memoranda (ECM) as " safety-related".
The
licensee provided the inspector with a listing titled " Systems Important
To Safety," which listed five rules for determining how to identify (safety-
related ECMs. However, the inspector indicated that the listing:
1) had
no identifying document number or approvals, and (2) could be subject to
,
non-uniform interpretations by the different groups preparing ECMs.
The inspector identified this listing as an unresolved item; its use by the
licensee will be the subject of a furtner review during a subsequent IE
inspection.
(80-13-01)
3.
Response to IE Bulletin 79-02
IE Bulletin 79-02, Revision 2, was transmitted to the licensee by NRC
letter dated November 8, 1979. The Bulletin requested the licensee to
perform reviews related to the pipe-support base-plate design which used
concrete expansion-anchor balts. The licensee responded to the Bulletin,
Revision 2, in his letter number GQL 1582 dated January 10, 1980.
He had
previously responded to the Bulletin, Revision 1, in his letter number GQL
0882 dated July 9, 1979.
The inspector reviewed licensee procedures, inspection and verification
reports, and redesign / modification documents to determine if the licensee
was complying with the commitments he made in his responses to the NRC-
transmitted Bulletin.
a.
Review of Procedures
The licensee stated that he had contracted with the architect-engineer,
Gilbert Associates of Reading, Pennsylvania, for the evaluation and design
modifications,1f.necessary, of pipe ~ supports using concrete expansion
anchors.
The inspector reviewed the following documents to determine if the
licensee had contracted for performing this task:
Letters:
R. T. Boyd to G. A. Delp, dated 3/15/80
G. A. Delp to D. G. Slear, GAI/TMI-1CS/3064
G. A. Delp to D. G. Slear, GAI/TMI-1CS/3040
G. A. Delp to R. T. Boyd, dated 2/11/80
R. N. Prabhakar to R. M. Klingaman, GQM-1523
Procedures:
GAI-In-service Inspection Manual
IIP-101, Technical Requirements for inspection of
concrete expansion anchor bolts and base plates.
. -
.
4
7902-2, Rev. 1, Inspection of pipe support base plates
that use concrete expansion anchor bolts in Seismic
Category I systems.
GAI-WO-04-4587-008, Procedure for installed concrete
expansion anchors.
Based on his review of above documents, the inspector determined that
the effort involved in evaluation, modification and/or corrective
actions necessary for compliance with Bulletin 79-02 was contracted to
Gilbert Associates by t.ne licensee. The inspector also determined
that the verification / inspection procedures initiated by the licensee
and Gilbert Associates were satisfactory for the performance of the
task.
b.
Review of Inspection and Verification Reports
The inspector reviewed the quality-control (0C) inspection reports for
the verification of the as-built condition of piping, pipe supports,
and concrete expansion anchors used in the supports.
The inspector
examined reports for a three month period between August 16, 1979 and
October 8, 1979.
The following reports were included in his examination.
S-1-120A, Rev. 1
S-1-270
S-1-125B. Rev. 1
S-1-279
S-1-127, Rev. 1
S-1-281
S-1-134, Rev. 1
S-1-296
S-1-1398, Rev. 1
S-1-305
4
S-1-140, Rev. 1
S-1-310
S-1-246
S-1-314A
S-1-252
S-1-318
The inspector determined that the reports were complete and were done
in accordance with licensee procedures.
The program of inspection and
verification of concrete expansion anchor bolts used in pipe supports
was satisfactorily implemented by the licensee.
c.
Review of Redesian/ Modification Documents
The inspector reviewed the documents describing evaluation, redesign,
and/or modification of pipe supports for unacceptable concrete expansion
anchors.
He examined the following documents for validity, complete-
ness, and adherence to the licensee cormiitments made in response to
Bulletin 79-02:
i
I
l
!
i
,
-
.,
___
-_ _____,
..
.
5
Support Evaluation Reports (SERs)
CF-1
NSE-1
NSE-5
CF-4
NSE-2
NSE-6
!-
Drawing 8563-CFR-GA-1258
Drawing 8563-CFR-GA-1262
Master Log / System data sheets for the following supports:
,
'
System BS; Bu11 ding Spray
Supports # BS-5
BS-9
BS-14
BS-6
BS-10
'
BS-8
BS-11
System CF, Core Flood
Supports # CF-1
CF-10
CF-4
CF-15
CF-7
System CO, Condensate
Supports # COE-3
COE-6
COE-21
System DC, Decay Heat Closed Cooling hater
Supports # DCH-3
DH-27
.
DCH-4
DH-28
DCH-5
DH-38
DCH-7
DH-127A
DCH-8
DCH-9
DCH-10
i
DCH-11
System IPH, Intake Pump House
Supports # IPH-13
IPH-90
IPH-88
IPH-91
IPH-89
System LR, Leak Rate
Support # LRH-14
System MPAH, Monitoring and Post Accident Purge
Supports # MPAH-1
MPAH-3
MPAH-2
!
,
_
._.
..'
.
.
'6
,
_
System MS, Main Steam
Supports # MS-290
MS-277A
MS-235
MS-225
System'NSE, Nuclear Services
Supports # NSE-1
NSE-12
NSE-2
NSE-24
NSE-3
NSE-27
NSE-4
NSE-37
NSE-10
NSE-97
NSE-11
NSE-155
,
System SBWH, Sodium and Borated Water
Supports # SBWH-1
SBWH-23
SBWH-2
SBWH-24
'
SBWH-10 SBWH-28
SBWH-12
GAI Support Evaluation Sheets
T-0001
T-0044
,,
i
T-0009
T-0099
1
T-0016
T-0132
!
l
Based on his review and examination of the above documents listed in para-
l
'
graphs 3.a, b, and c, the inspector determined that the licensee and Gilbert
Associates complied with the licensee's commitments in response to Bulletin 79-02.
i
!-
No items of noncompliance were identified.
'
4.
High Pressure Injection (HPI) Cross-Connect Modification (Task RM-14)
a.
Review of Nondestructive Examination (NDE) Procedures
The inspector reviewed NDE procedures associated with inspection of
Para
for Restart of TMI-1" (graph 2.1.4.3 of the " Recommended Requirements
the " Restart Report") states:
"All system component; forming the containment boundary will...be
designed to Safety Class 2 per ANSI B-31.7."
This review was done to ascertain compliance with the Nuclear Power
Piping Code USAS B31.7.
.
.
~
--
,
_,
, , . , .
,
. . . . ,
.n.-,
-.n
.
.
_
-7
1
The inspector reviewed.the following procedures:
Nuclear Energy Services (NES) Procedure 25-VW-001, " Visual Inspection
--
of Welds"
NES Procedure LPT-1-NP, " Nondestructive Testing Procedure for
--
Liqui? Penetrant Examination"
NL, Procedure XR-1-NP, " Nondestructive Testing Procedure for
--
Radiographic Examination"
During his review of procedure XR-1-NP, the inspector found three
items considered unresolved:
(1) Appendix B, paragraph B-1-120.4 of USAS B-31.7 requires all film
to be processed in accordance with ASTM E-94.
There was no
information relative to film processing in procedure XR-1-NP.
The licensee stated that he has been processing film in accordance
with the requirements of ASME,Section V, E-94, but that he has con-
tracted.with N.E.S., Inc. tc nrepare a processing procedure.
This item is considered to be unresolved pending a review of the
procedural control of radiographic film processing (in accordance
with the techniques of ASTM E-94, as required by Appendix B,
paragraph B-1-120.4 of B-31.7) by an NRC inspector.during a
subsequent inspection.
(80-13-02)
(2)
Section 3.12 of procedure XR-1-NP states that whenever a film-
side penetrameter is used, a lead letter
"F",
" high, shall be
placed adjacent to the penetrameter. Appendix B, paragraph B-1-
120.2(b) of B-31.7 requires a lead letter "F" at least " high.
Subsequent to the inspector's departuri.y from the site, the licensee
' stated that he had changed the proceduve to comply. Furthennore, film
records that the licensee produced prioi t!o 'the procedure change
will be sampled by the licensee to ensure that the 1/4 inch high letter
"F" produced acceptable records.
This item is considered to be unresolved pending the inspector's
review of the procedural change and film records during a subsequent
inspection.
(80-13-03)
(3) Appendix B, paragraph B-1-160 of B-31.7 requires that radiographic
procedures include a description of the welding procedure used
for welds which are examined in accordance with the RT procedure.
The inspector did not find this in procedure XR-1-NP. The licensee
stated that this would be incorporated in a field change to
procedure XR-1-NP.
This item is considered to be unresolved pending the inspector's
review of the procedural change during a subsequent inspection.
(80-13-04)
..
-
8
b.
Review of Welding
The inspector reviewed welding records ~and procedures associated with
the HPI system modification. This review was done to ascertain compliance
with the Nuclear Power Piping Code USAS B31.7.
The following records and procedures were included in the inspector's
review:
Catalytic Incorporated Welding Specificaticn SP-4200-SS(N)-101A,
--
" Gas Tungsten Arc Welding of Stainless Steel"
Catalytic Incorporated Specification SP-4200-SS(N)-102A, " Gas
--
Tungsten Arc Shielded Metal Arc Welding of Stainless Steel"
Qualification records for the above welding specifications.
--
Welder performance qualification records for Catalytic Incorporated
--
welders identified by the following numbers:
67-199
67-216
.67-157
67-512
67-074
67-198
67-154
67-058
The inspector found that the welding specificat'on and welder performance
qualification were in accordance with Section IX of the ASME B&PV Code
as required by B-31.7
No items of noncompliance were identified.
5.
Unresolved Items
,
-Unresolved items are matters about which more information is required in
order to ascertain whether they are acceptable items, items of noncompliance,
or deviations.
New unresolved items disclosed during this inspection are
discussed in paragraphs 2 and 4.a.
6.
Exit Interview
The inspectors met wi';h the licensee representatives (denoted in paragraph
1) at the conclusion of the inspection on June 19, 1980.
The inspector
sumarized the purpcse and scope of the inspection and the findings.
The
licensee acknowledged the findings.
-..
.
,.
--
.
-.