IR 05000320/1975009
| ML19206B029 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/08/1975 |
| From: | Folsom S, Heishman R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19206B016 | List: |
| References | |
| 50-320-75-09, 50-320-75-9, NUDOCS 7904210725 | |
| Download: ML19206B029 (8) | |
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IE:1 Ter= 12 (Jan 75) (Rev)
U. S. !?UCLEAR REGULATOF? CC:CIISSIO::
OFFICE OF INSPECT 10!i !
E!iFORCD!E 7T
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REGIC:i I
50-320/75-09 Docket No:
50-320 II Inspection Report No:
CPPR-66 Metropolitan Edison Cerpany License Io:
Licensec:
Box 542 Priority:
A Reading, Pennsylvania 19603 Category-Safeguards Middictown, Pennsylvania (Three Mile Island 2)
Location:
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Type of-Licensce:
Special - Announced Type of Inspection:
June 25 and 26, 1975 tes of Inspection:
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June 10-13, 1975 Dates of Previous Inspection:
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?-t-N Reporting Inspector:
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Seth A. Folsom, Riiactor Inspector None Accompanying Inspectors:
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Other Accompanying Personnel:
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Reviewed By:
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R. F. lleisliman, Senior Reactor Inspector
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79042107tr (A-O!;9
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SLW!ARY OF FINDINGS Enf er ee:,en t Action
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A.
Items of Moncompliance Infracticn Contrary to 10 CFR 50.55(e):
The identification, by magnetic particle examination, of axial linear indications in reactor coolant pump studs and nuts was not promptly reported to the Suelear Regulatory Ccamission.
(Details, Paragraph 3)
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B.
Deviations None Licensee Action on Previous 1v Identified Enforcement Matters Not inspected
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Design Changes None identified
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Unusual Occurrences
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None identified Other Sienificant Findings
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A.
Current Findings
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Unresolved Items During ultrasonic examination of the primary coolant pumps studs and nuts, radial linear indications were identified. This item is unresolved.
(Details, Partgraph 2)
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Status of Previous 3v Unrcsnived item 3 Not in pected Manarerent Intervied interview was held at the site on June 26, 1975.
A canagement Persons Present General Public Utilitics Service Corporation Mr. L. R. Howell, Mechanical Engineer Mr. S. Levin, Site Project Engineer Mr. P. A. Levine, QA Auditor Mr. J. Spinak, Lead Quality Assurance Engineer
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Mr. M. J. Stromberg, Site QA Auditor Babcock and Wilcox Mr. R. J. Kunz, Quality Control. upcrvicor Mr. F. A. Skrzypice, Field Enginear Mr. B. E. Treadway, Project Manager CAI Mr. R. Sanaccre, Nuclear Engineer
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The items discussed are sun:marized below.
(In each case the licensee acknowledged the information presented by the inspector).
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A.
Scooe of the Inspection The inspector stated that the purpose of this inspection was t)
review the documentation and work in progress on the radial litear indications found during ultrasonic inspection of the primary coolant pu=p studs and nuts.
(Details, Paragraph 2)
B.
Items of Noncompliance Following the inspection, on July 1, 1975, the inspector notified Mr. S. Levin by telephone that the follcuing noncompliance had been
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Radial linear indications had been identified during magnetic The partic.c inspection of reactor coolant pump studs and nuts.
1;ucicar Regulatory Commission Regional Office was not notified of this ratter until about six weeks follcwing initial identification of the rejectabic items.
This is considered to be an infraction of 10 CTR 50.55(c).
(De-tails, Paragraph 3)
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/4-DETAILS 1.
Persons Contacted General Public Utilitics Service Corporation Mr. L. B3ystone, Quality Assurance Engineer Mr. R. C. Cutler, Proj ect Engineer Mr. U. T. Gunn, Site Itnager Mr. L. R.110well, Mechanical Engineer Mr. S. Levin, Site Proj ect Engineer Mr. 2. A. Levine, QA Auditor Mr. J. Spinak, Lead Quality Assurance Engineer Mr. M. J. Stromberg, Site QA Auditor
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Mr. J. H. Wright, Resident Civil Engineer Babcock and Wilcox Mr. R. J. Kunz, Quality Control Supervisor Mr. F. A. Skrzypiec, Field Engineer Mr. B. E. Treadway, Project Manager United Engineers and Constructors Mr. D. C. Lambert, Field Supervisor, Quality Control Mr. F. F. Long, Assistant Field Supervisor, Quality Control Royal Indemnity Insurance Cocoany
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Mr. E. L. Cottschall, Authorized Inspector Automation Industrics, Inc., Nuclear Service Division Mr. C. L. James, Inservice Inspection Supervisor CAI Mr. R. Sanacore, Nuclear Engineer
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2.
MT Radial Linent indications on RCP Studs and Nuts The licensee notified the inspector by telephone on June 24, 1975 that during magnetic particle examination of the reactor coolant punps studs and nuts, radial linear indications had been identified in excess of 1" in length.
The AS"E Boiler and Pressure Vessel Code,Section III, 1971 Edition, and the site (Ccnam) Procedure 2305-El-I " Continuous Wet Fluorescent Magnctic Particle Examination of Eolts, Studs and Nuts" dated February 4, 1975 consider parts rej ectable when radial linear indications exceed 1" in length.
A total of 80 studs and 80 nuts were inspected by MT.
Of these, 29 studs and 12 nuts were rejected.
Deviation Report No. 0469 was issued by UELC, the constructor, on May 29, 1975.
The report included attachments describing in detail each indication iden-tified.
The reported indications were up to 9" in length.
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The licensee notified the NSSS (Babcock & Wilcox) to replace the rejected parts, or to provide written justificatfan for their use.
At the time of the inspection, the licensee had received no re-sponse from B&W regarding the rejected parts.
A B&W cemorandum, dated June 18, 1975, addressed to the Three Milt Island 2 B&W Site Manager, and signed by the B&W Project :Managet, acknowledged that
"so=e or the R.C. Pump Studs and Nuts are on ' hold' due to apparent lir. car indications," and authorized assembly of the first R.C. pump using "the studs which passed ISI tests."
The inspector was unable to deter =ine the maker
.f the steel, or of the forgings.
Dysons & Sons, Inc., Painesville, Ohio, machined the parts f rom the forgings.
Prior to machining, the forgings were
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"All material on this order has been impact tested Charpy a.
' Notch Test, at 40 F in accordance with.ASME B&PV Code, Section
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III per N330 and Winter Addenda of 1966 and 1967, result being impact strength at +140F Standard Charpy V Notch Bars."
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"Each picec has been magnetic particle inspected applicable specification ELVP Code, Section Ill per N626 and N627.
Bingham Quality Assurance Program Rev. 6, Page 7 of 10, Spec.
7, Par. 7.1 to 7.12 Inclusive Rev. B&D.
Results - acceptable to Standard."
"Al? material on this order has been ultracenically tested in c.
accordance with BSPV Code,Section III, Winter Addenda 1967, Par. 325 and our Bolting Standard Rev.
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Par 7.2 to 7.41 inclusive.
Results - Acceptable to Standard."
Based upon the statements by the E&: representatives at the site it appears that the NDE stated in a, b and c, was performed by Dyson on the forgings, and that no NDE was performed on the machined parts.
i The Dyson " Reports of Chemical and/or Physical Propertics" dated
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March 17, 1969.4sts 486 studs and 486 nuts, sore of which were rejected.
The '~ is for tne rejection, and tne disposition of the rejected pr ould not be determined.
The B&W Site Manager stated tt_ cae 80 studs and 80 nuts shipped to Three Mile Island 2 were part of this larger lot.
The studs are 31-3/4" long and 4" diameter, and are made frem ASTM A-193 Grade B7 steel.
The nuts are 6" long and 6" diameter, and
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are made from ASTM A-194 Class 2H steel.
The B&W Purchase Order for the 4 Bingham pu=ps was dated October 6, 1967, and referenced B&W Purchase Specification CS-3-36, the pumps to be built in accordance with ASME Code,Section III, Class A Vessels.
3.
Infraction - Reportine Requirements of 10 CFR 50.55(el The on-site inspection of reactor coolant pump studs and nuts was started early in May, 1975.
The site documentation shows, for example, that MT of Reactor Coolant Pump Stud No. 272 was completed on May 14, 1975, and this NDE identified axial linear indications up to 6" long.
Similarly, Reactor Coolant Pum) Nut No. 17 was magnetic particle inspected on ?by 15, 1975, with rejectable axial linear indications reported.
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-7-Deviation Ecport No. 0469 was completed on May 29, 1975 which included the statement, " Twelve (12) RCP nut s and twenty-nine (29)
studs listed on the attached sheets and Magnetic Particle Reports shou linear axial indications greater than 1" in length.
This is in violation of ISl procedure 2305-El-I and ASME Section III, 1971 Edition."
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Ko records were avai]able onsite to indicate that a determination of reportability had been accomplished pronptly uprn identification of the deficiency.
The licensee did not notify the NRC Regional Of fice of this ratter until June 24, 1975.
This is considered to be an infraction with respect to 10 CFR 50.55(e) which states in part, (1) "If the permit is for construction of a nuclear power plant, the holder of the permit shall notify the Cc= mission of each deficiency found in design and construction;" (2) "...s.
1 promptly notify the appro-priate Nuclear Regulatory Cc==ission laspection and Enforcement
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Regional Office of 2ach reportable deficiency."
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