IR 05000546/1980008
| ML19323G267 | |
| Person / Time | |
|---|---|
| Site: | Marble Hill |
| Issue date: | 04/17/1980 |
| From: | Harris J, Hawkins F, Hayes D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19323G264 | List: |
| References | |
| 50-546-80-08, 50-546-80-8, 50-547-80-08, 50-547-80-8, NUDOCS 8006020063 | |
| Download: ML19323G267 (7) | |
Text
C)
'
v
.
t
'
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-546/80-08; 50-547/80-08 Docket No. 50-546; 50-547 License No. CPPR-170; CPPR-171 Licensee:
Public Service of Indiana 1000 East Main Street Plainfield, IN 46168 Facility Name: Marble Hill Generating Station, Units 1 and 2 Inspection At: Marble Hill Site, Jefferson County, IN Inspection Conducted: February 27
9, March 6 and 18-21,1980
"I i
i E
Inspectors:
P.
. Hawkins d /( 71B 0 (February 27-29, March 6 and 18-21, 1980)
'
'
'I i
J arr (
ch 18-21, 1980)
4 /I 716 0
.
'
/
l +,
' ief Qfl7/80 Approved By:
Hayes, i
.
Engineering Support Section 1
/
'
Inspection Summary Inspection on February 27-29, March 6 and 18-21, 1980 (Report No.
50-546/80-08; 50-547/80-08)
Areas Inspected: Observation of work and review of quality records for Construction Verification Procedure SPP-5; review of Construction Veri-fication Procedure SPP-2; review of Construction Verification Procedure SPP-3; review of implementing procedures and related quality records for site blasting work. This inspection involved a total of 98 inspector-hours on site by two NRC inspectors.
Results: No items of noncompliance or deviations were identified.
M g006020
.-
- __ _ _______________ - ________ _ _________
.
DETAILS Persons Contacted Public Service of Indiana (PSI)
G. Brown, Project Director
- J. Brewer, Construction Manager
- R.J. Kime, Assistant Construction Manager
- L. O. Ramsett, Quality Assurance Manager
- J. M. Norris, Acting Non Code Quality Assurance Manager
- T. R. Burns, Project Engineering Manager
- J. R. Ubaudi, Project Controls Manager
- J.
Frost, Area Manager - Auxiliary Building
- R. Latronica, Area Manager - Auxiliary Building
- L. A. Nicodenma, Supervisor - Program Support
- D. B. Ingwire, Quality Assurance Superintendent - Civil
- G. Warner, Quality Assurance Engineer
- I. J. Lefman, QuaJity Assurance Audit Coordinator D. L. Shuter, Quality Assurance Engineer N. Reichel, Area Manager - Reactor Building R. Royer, Area Engineer - Reactor Building D. Blackwell, Area Engineer - Reactor Building W. Minick, Quality Control Inspector M. Bright, Quality Control Inspector J. Lella, Quaiity Control Inspector G. K. Newberg Construction Company (N-MH)
A. Archer, Project Director R. Alcorn, Quality Control Inspector J. Mulligan, Quality Control Inspector T. Mayer, Quality Control Inspector United States Testing Company (UST)
D. Lanham, Site Project Manager K. Rademacher, Assistant Site Project Manager R. Grossman, Technician Other Personnel
- J. J. Harrison, RIII NRC Resident Inspector K. Seeber, Sargent & Lundy Site Structural Enginner
- Denotes those attending the exit interviews.
-2-
-
-
-
_ __ __-_-
.
e Functionai or Program Areas inspected 1.
Construction Verification Program (SPP-5)
Observation of Work - In process inspection of concrete'sur-a.
faces was observed in the following specific areas:
(1) February 27, 1980 Observed Physical Survey Team (PST) 1 inspection of the Auxiliary Building ceiling in an area L-P lines and 23-24 lines; S&L Drawing S-680 Revision T; Elevation 346',
Observed PST 2 inspection of the Auxiliary Building ceil-ing in an area P-Q lines and 13-17 lines; S&L Drawing S-679 Revision V; Elevation 346'.
Observed PST 3 inspection or the Auxiliary Building ceil-ing (Elevation 353'-o") in an area V.3-W lines and 15-16.4 lines; S&L Drawing S-678 Revision G; Elevation 346'.
(2) February 28, 1980 Observed '.'ST 1 inspection of the Auxiliary Building ceil-ing in an area P-Q lines and 18-19 lines; S&L Drawing S-680 Revision T; Elevation 346'.
Observed PST 2 inspection of the West face of Q line wall, 10-15 lines in the Auxiliary Building; S&L Drawing S-674 Revision G; Elevation 346'.
(3) March 19, 1980 Observed PST 1 inspection of the Unit 2 reactor cavity; S&L Drawing S-878 Revision B; Elevation 350'-6".
(4) March 20, 1980 Observed PST 1 inspection of the Unit 1 and Unit 2 Aux-iliary Building Tunnels; S&L Drawings S-711 Revision F and S-712 Revision E; Elevation 379'-6".
Each observation included verifcation that the PST was conducting the inspection in accordance with the spec-ified procedural requirements.
b.
Review of Quality Records (1) The training packages were reviewed for all PSI and N-MH inspection personnel performing work in accordance with SPP-5.
The packages included the revision to which the training was performed, a personnel attendance list, and an outline of the major points which were covered during the training session.
-3-
.
. - _ - _
-_
_______
.
b (2) Individual daily inspection packages generated as a result of the concrete verification program were reviewed.
Each package included marked-up drawings, Concrete Patch Data Sheets, Repair Area Data Sheets, and the identity of the inspectors performing the work. Specific packages reviewed are as follows:
(a) February 26, 1980 Team 1 - Inspection of the East side of Q line wall in the Auxiliary Building, 21-26 lines; West side of L line wall in the Auxiliary Building, 18 line to 8'
South of 20 line; and the Auxiliary Building columns in an area L-Q lines and 19-26 lines; S&L Drawing S-673 Revision H; Elevation 346'.
Team 2 - Inspection of the Auxiliary Building walls and columns in an area L-Q lines and 10-18 lines; S&L Drawing S-672 Revision W; Elevation 346'.
Team 3 - Inspection of the Auxiliary Building ceiling and walls in an area Q.8-V lines and 19-21 lines; S&L Drawing S-678 Revision G; Elevation 346'.
(b) February 27, 1980 Team 1 - Inspection of the Auxiliary Building ceiling in an area L-Q lines and 20-26 lines; S&L Drawing S-680 Revision T; Elevation 346'.
Team 2 - Inspection of the Auxiliary Building ceiling in an area L-Q lines and 13-18 lines, N-Q lines and 10-13 lines; S&L Drawing S-679 Revision V; Elevation 346'.
(c) March 11, 1980 Team 1 - Inspection of the Unit 1 Reactor Building secondary shield wall interior (Aziauth 90' 270*);
S&L Drawings S-1479 Revision G and S-1482 Revision i
F; Elevation 377'.
(d) March 12, 1980 Team 1 - Inspection of the Unit 1 Reactor Building secondary shield wall interior (Azimuth 270 90 )
and the Unit I reactor cavity (key hole);
S&L Drawings S-1480 Revision J, S-1481 Revision G, and i
S-878 Revision B.
(e) March 13, 1980 Team 1 - Inspection of the Unit 1 Reactor Building tendon tunnel; S&L Drawings A-324 Revision D, A-325 Revision C, A-316 Revision F, and A-327 Revision B.
-4-j
_
-
.
(f) March 14, 1980 Team 1 - Inspection of the Unit 1 Reactor Building tendon tunnel, refueling pool support walls, and the No. 3 buttress enclosure; S&L Drawings S-904 Revision N, S-905 Revision N, A-324 Revision D, A-325 Revision C, and A -326 Revision F.
(g) March lo, 1980 Team 1 - Inspection of Ge Unit 1 Reactor Building refueling pool support walls, recirculating sumps, and the No. 3 buttress enclosure; S&L Drawings S-904 i
Revision N, S-905 Revision N, and S-906 Revision L.
No items of noncompliance were identified.
2.
Construction Verification' Program (SPP-2)
I Review of Implementing Procedures - The RIII inspector reviewed Construction Verification Program Procedure No. SPP-2, Revision 5 entitled " Category I Reinforcing Steel", to verify that it included appropriate inspection personnel requirements, that it was tech-nically adequate, and that proper quality documentation would be generated as a result of its implementation. On March 5, 1980, RIII concurred with the use of Procedure No. SPP-2, Revision 5 as part of the Construction Verification Program.
No items of noncompliance were identified.
3.
Construction Verification Program (SPP-3)
Review of Implementing Procedures - The RIII inspector reviewed Construction Verification Program Procedure No. SPP-3, Revision 2 entitled " Category 1 Structural Steel", to verify that it included l
appropriate inspection personnel requirements, that it was tech-
'
nically adequate, and that proper quality documentation would be generated as a result of its implementation. On March 20, 1980,
'
RIII concurred with the use of Procedure No. SPP-3, Revision 2 as part of the Construction Verification Program.
No items of noncompliance were identified.
4.
Blasting - Review of Implementing Procedures and Related Quality Records The inspector examined licensee controls on blasting operations.
Examinations included review of b1Last testing, procedures, spec-ifications, records, nonconformance reports, licensee evaluation of a potential 50.55(e) item reported to NRC on February 13, 1980 and interviews with responsible engineers and technicians.
-5-
_ _ _ _...
.
e Controlling procedures and specifications examined by the inspector were as follows.
a.
N-MH Procedure WPQ-1, Blasting b.
UST Procedure QCP-20, Blast Monitoring c.
S&L Specification Y-2850 d.
S&L Specification Y-2722 Examination of the above disclosed several apparent areas of in-adequate controls which were identified to the licensee as follows:
a.
The potential 50.55(e) item reported to NRC on February 13, 1980 indicated that confusion in procedure instructions as to the correct location for monitoring particle velocities for blasting had resulted in numerous shots being monitored at locations that were not the most critical monitoring point.
Review of the licensee's evaluation showed that calculated particle velocities for the criticle monitoring points were within specified acceptance criteria. However, interviews with responsible technicians indicated there still appears to be some confusion in existing specifications and procedures as to the most critical monitoring point.
b.
Documentation for dispositioning of NCR 867C and NCR 972A issued by US Testing Company for shots on July 23, 1979 and December 5,1979 respectively, were not available.
c.
Procedures and specifications do not appear to provide an immediate method of correcting subsequent shots when the most recent shot has exceeded the specified particle velocity limit.
d.
Where the most critical monitoring point is adjacent to a category II structure and monitoring results show that the acceptable particle velocity was exceeded, no provision is made to determine the particle velocity at the nearest Category I structure.
e.
Paragraph 303A.6-h of S&L Specification Y-2850 states that after each blast, the measured particle velocity shall be compared with the particl<
elocity predicted from the attenuation curve developt from the blasting test.
Significant deviat ions from the attenuation curve shall be reported regardless of whether the specified criteria for blasting controls have been exceeoed.
Licensee per-sonnel indicated that attenuation curves had been changed as a result of comparing measured and predicted particle velocities, but no documentation was available to illustrate that comparisons had been made.
-6-
d
Items a through e above are considered unresolved and will be reviewed further during a subsequent inspection (546/80-08-01; 547/80-08-01).
Upon completion of the inspector's presentation of bis concerns on blasting controls,at the exit meeting, the licensee stated that operations would be (*_acontinued and would not resume until the above NRC concerns were addressed and concurred in by the NRC.
No items of noncompliance were identified.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of non-compliance, or deviations. One unresolved item disclosed during this inspection is discussed in Section 4 of this report.
Exit Interview The inspector met with staff representatives (denoted in the Persons Contacted paragraph) at the conclusion of the inspection. The inspector summarized the scope and findings of the inspection. The licensee ac-knowledged the findings.
-7-