ML19210E414
| ML19210E414 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 10/02/1979 |
| From: | Danielson D, Erb C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19210E409 | List: |
| References | |
| 50-440-79-07, 50-440-79-7, 50-441-79-07, 50-441-79-7, NUDOCS 7912050011 | |
| Download: ML19210E414 (5) | |
See also: IR 05000440/1979007
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U.S. NUCIIAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEME.NT
REGION III
Report No. 50-440/79-07; 50-441/79-07
Docket No. 50-440; 50-441
Licecse No. CPPR-148; CPPR-149
Licensee: Cleveland Electric Illuminating
Company
P. O. Box 5000
Cleveland, OH 44101
Facility Name: Perry Nuclear Power Plant, Units 1 and 2
Inspection At: Perry Site, Perry, Ohio
Inspection Conducted: September 10-12, 1979
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Inspector:
C.
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Approved By:
D. H. Danielson, Chief
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Engineering Support Section 2
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Inspection Summary
Inspection on September 10-12, 1979 (Report No. 50-440/79-0'7; 50-441/79-07)
Areas Inspected: Observation of work for recirculation piping and reactor
vessel inlet nozzle modifications; procedure review for recirculation inlet
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nozzle modification and for setting the reactor vessel; storage of safety
related equipment; previously identified inspection findings. The inspec-
tion involved a total of 24 inspector-hours onsite by one NRC inspector.
Results: Of the four areas inspected, no apparent items of noncompliance
were identified in three areas; one apparent item of noncompliance was
identified in one area (infraction - failure to verify hold points during
installation of the reactor vessel - Paragraph 5).
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DETAILS
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Persans Contacted
Clevelard Electric Illuminating Company (CEI)
- W. J. Kacer, General Supervising Engineer
- L.
E. Hartline, Supervisor
- P. A. Fitzpatrick, Construction Manager
- R. L. Farrell, Suparvisor, Procedures and Records
- A. Kaplan, Supervisor Construction Section
- R. L. Vondrasek, Supervisor
- P.
L. Gibson, Supervisor
- D. F. Cooper, Supervisor
- T. J. Arney, Manager QA Program
- B. C. Barkley, Nuclear Design
J. Mehaffey, Lead Mechanical Engineer
A. Bolesic, Warehouse Receiving
Pullman Pipe and Supports Company (Pullman)
J. Miller, Manager QA
Newport News Industrial Corporation (NNIC)
R. T. Durand, Manager NSSS
D. Dervay, Engineer NSSS
G. Hyde, Quality Assurance NSSS
- Denotes those attending the exit interview.
Functional or Program Araas Inspected
1.
Modification and Rework of Recirculation Piping and Reactor
Vessel - Units 1 and 2
The recirculation piping (24", 22", 18", 12" diarneter) has been
returned to Pullman for machining, deposition of weld metal and
solution treatment to improve service life. The rework of the inlet
nozzles (N2) and thermal sleeves will begin the latter part of
October 1979. General Electric I. & S. E. have the contract for
this work. The quenchers for the suppression pools of both plants
have been received on site. The 38 quenchers are stainless steel
and were fabrtcated by Chicar;o Bridge and Iron -Nuclear (CBIN).
d.
Review of Licensee Audit
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During August and September, 1979 1.ta licensee undertook an. extensive
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audit of Newport News Industrial Corporation QA program by etting
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up several audit teams, who investigated the operation and implemen-
tation of their QA program. This audit confirmed the findings outlined
in RIII inspection Reports No. 50-440/79-03 and No. 50-441/79-03
Tne
auditors found documentation uisting in field welds for the transfer
pool, weld history records missir.g in the biological shield welds, and
completion of base metal repairs without documentation of this fact in
the biological shield.
Numerous other exacples of lack of procedure or failure to follow
existing procedures were found. The licensee issued a Stop Work
Order on all NNIC work, except one small area of work where brackets
were being welded to the biological shield to accomodate structural
floor beams at the 630 foot level.
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This action restricts the contractor to a few welders and their
supe rvision. The activity will be monitored to establish satis-
factory performance in the NNIC QA program before additional work
will be released. At tha time the "Stop Work" was issued, training
and indoctrination classes were initiated for the foremen, general
foreman, and superintendent so that supervision would be more knowl-
edgeable of their job and Q A requirements.
Corrective action has been started on many items, but is not complete.
Certain welds have been marked for removal and replacement.
In other
areas, personnel have been terminated or transferred. The proposed
corrective actions appear to be acceptable and should result in satis-
factory QA implementation and documentation. Licensee actions and
con.ractor performance will be examined closely during future routine
inspections.
No items of noncompliance or deviations wsre identified.
3.
Storage of Safety Related Equipment - Units 1 and 2
The warehouses for inside storage are very crowded and this necessitates
undesirable handling for withdrawal of equipment. The licensee has
secured two additional warehouses in Fairport Harbor which are heated
and should relieve this problem.
The inspector recommended that representative pieces of equipment
s;ored outside be unwrapped and examined for condition. Scme equipment
has been outside since 1976 and the effectiveness of the canvas and
plastic wrap should be evaluated. This is an unresolved item, until
some inspectiona of outside stored equipment have been completed.
(440/79-07-01; 441/79-07-01)
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No items of noncompliance or deviations were identified.
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4.
Procedures for Recirculation Inlet Nozzle Safe End (N2)
Modification - Units 1 ard 2
The inspector reviewed the following procedures from General Electric
I. & S. E. that were submitted to the licensee for review and approval:
RM3-IP-0010, Revision 0
Recire Inlet Thermal Sleeve Extension
and Safe End Reinstallation Procedure
WPS 8.2.3.5, Revision 3
Detailed Weld Procedure Specification -
Thermal Sleeve
WQ 8.2.3.1, Revssion 2
Welding Performance Qualification -
Thermal Sleeve
WPS 43.2.4.5, Revision 3
Detailed Weld Procedure Specification -
WQ 43.2.4.1, Revision 1
Weld Performance Qualification -
WPS 8.2.4.2R, Revision 1
Detailed Weld Procedure Specification -
Repair Stainless Steel
WPS 43.2.4.2R, Revision 3
Detailed Weld Procedure Specification -
Repair Inconel
RM3-NPT10-S76
Penetrant Examination Procedure
A Dimetrics Automatic Tungsten Inert Gas Welder will be used to make
the two internal welds of the thermal sleeve to the nozzle and to the
safe end. This welder will also be used to make the external weld of
the reactor vessel nozzle to the safe end. A detailed procedure for
the automatic equipment settings is available. The work will conform
to ASME Section XI and Section III 1974 Edition, Summer 1975 Addenda.
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No items of noncompliance or deviations were identified in this
area.
5.
Setting Procedure for the Reactor Vessel - Unit 2
The inspector reviewed procedure 1240-F-I005-2, Revision 3, which
contained tha sequence of operations for setting the vessel.
Many
blank spaces were evident in the first column where the production
people should sign; the second column also had many blank spaces
where NNIC QA/QC should sign.
Paragraph 10.1300 of the NNIC QA
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Manual states that, "QA will maintain the original of all manufacturing
installation and inspection sheets (MII'S), which shall be available
to QC inspectors and the ANI. Verification of each step will be
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performed by QA."
This is an item of noncompliance identified in
Appendix A.
(441/79-07-02)
Unresolved Item
Unresolved items are matters about which more information is required in
order to ascertain whether they are acceptable items, items of noncompliance
or deviations. An unresolved item disclosed during the inspection is
identified in paragraph 3.
Exit Interview
The inspector met with site representatives (denoted in Persons Contacted
paragraph) at the conclusion of the inspection on September 12, 1979.
The inspector summarized the scope and findings of the inspection. The
licensee acknowledged the findings.
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