IR 05000387/1979030
| ML17138B037 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 10/10/1979 |
| From: | Jernigan E, Lester Tripp NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17138B033 | List: |
| References | |
| 50-387-79-30, NUDOCS 8001240090 | |
| Download: ML17138B037 (5) | |
Text
U.
S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION I
Report No.
79-30 Docket No.
50-387 License No.
CPPR-101 Priority Licensee:
Penns lvania Power 8 Li ht Com an Category 2 North Ninth Street Al 1 entown Penns 1 vania 18101 Facility Name:
Sus uehanna Steam Electric Station Unit 1 Inspection At:
Berwick Penns lvania Inspection Conducted:
Au ust 21-24 1979 Inspectors:
E.
P.
J nigan, reactor Inspector
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ate date
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",;g Approved by:
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"Lowell E. Tripp,'ection Chief, Engineering Support Section No. 1, RC8ES Branch date
/~=//c'/7'i'ate Ins ection Summar
Ins ection on Au ust 21-24 1979 Re ort No. 50-387/79-30)
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of pipe welding and pre-service examination activities associated with the recir-culation system modification.
The inspection involved 26 inspector-hours on site by 1 NRC regional based inspector.
Results:
In the 2 areas inspected, an item of apparent noncompliance was identified in one area.
Failure to apply design control measures relative to field modifications to demonstrate that Section XI inservice inspection require-ments can be met.
(Paragraph 3)
Region I Form 167 (August 1979)
80015 40 o p
DETAILS Persons Contacted Penns lvania Power & Li ht Com an PP8L
~J.
Green, Resident Nuclear gA Engineer
~R. Beckley, Site gA Engineer E. Carroll, Site gA Engineer T. Oldenhage, Resident Engineer
~M. Gorsk, Resident Engineer
~J. Eichlin, Engineer
"D. Ritter, Engineer
~E. Brignole, Senior Project Engineer G. Burvis, gA Engineer General Electric (I8SE)
D. Weis, Welding Superintendent Bechtel Cor oration
"J. O'ullivan, Assistant Project Field Engineer
"G. Shrader, Project Field gC Engineer
"M. Daubenheyer, Project Superintendent
"Denotes those present at the exit meeting.
Plant Tour The inspector observed work activities in progress, completed work, and plant status in several areas throughout the plant during the tour.
The inspector examined work items for any obvious defects or noncompliance with regulatory requirements.
Recirculation S stem Modification The licensee NSSS contractor, General Electric, is replacing the safe-ends on the reactor pressure vessel recirculation nozzles to allow instal-lation of a newly designed thermal sleeve.
This modification is in keep-ing with previous modifications aimed at increasing reliability and pro-tection against intergranular stress corrosion cracking (IGSCC).
The following items were examined for compliance with the 1974 Edition of Section XI and III of the ASME Code including the Summer 1975 and 1976 Addenda for the respective codes.
Witnessed welding of'ozzle safe-end and thermal sleeve stub mock-u Nondestructive examination (NDE) and inspection of mock-up.
Material certifications and related quality records.
Melding procedure qualification records.
Meldor qualification records.
The above activities were in compliance with the applicable code require-ments.
However, the inspector found that the safe-end replacement required cutting the risers to gain access to the safe-end thermal sleeve.
Also, a second cut was necessary to remove the external jet pump riser pipes.
This cut was located about 3/4-inch above the main recirculation header to riser attachment welds.
To protect against sensitization during field welding, corrosion resistant cladding (CRC) was applied to the lower end of the riser pipes on the inside and outside surface.
Additionally, the material lost during cutting, as well as anticipated weld shrinkage, is made up in the vertical section by adding a 308L weld build-up to the lower end of each riser pipe.
This weld build-up will vary up to approxi-mately 1 1/2-inch in length.
The final weld configuration is a double circumferential weld (about 3/4-inch center-to-center).
The documentation reviewed by the inspector for inservice inspection did not indicate that weld inspectability had been assured.
Discussions with cognizant personnel and a review of preliminary data indicated that the final weld configuration precluded a satisfactory ultrasonic examination.
This was based on reports of efforts to ultransonically examine a mock-up containing a double weld and a configuration similar to the welds in ques-tion.
Reported results of this effort are considered to be inconclusive.
The construction permit for Unit 1 was issued in November, 1973.
Relating this date to the requirements of 10 CFR 50.55a (g), Inservice Inspection Requirements stipulate that components classified as ASME Code Class 1 and 2 shall be designed and provided with access to enable the performance of inservice examinations.
Additionally, Article IMA-1400 of the ASME states that the Owner's responsibility for the performance of inservice examinations includes
"The design and arrangement of pipe system components to include allowance for adequate clearances for the conduct of the examinations."
Further, the Bechtel specification M-196, Revision 0, Design Guidelines.
for Access for Inservice Inspection, states requirements for weld spac-ing (to be a minimum of 6-inches)
clearance and access for manual ISI examinations.
Failure to follow the above mentioned requirements relative to design and arrangement of piping/welds to permit ISI is contrary to the require-ments of 10 CFR 50.55a paragraph (g)(2),
Codes and Standards.
This item is an infraction.
(79-30-01)
Mana ement Meetin At the conclusion of the inspection on August 24, 1979, a meeting was held at the site with representatives of the licensee and contractor organiza-tions.
Attendees at this meeting included personnel whose names are asterisked in paragraph 1.
The inspector summarized the purpose and results of the inspection as described in this repor '