ML20052B515
| ML20052B515 | |
| Person / Time | |
|---|---|
| Issue date: | 04/05/1982 |
| From: | Barnes I, Kelley W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20052B513 | List: |
| References | |
| REF-QA-99900053 NUDOCS 8205030166 | |
| Download: ML20052B515 (9) | |
Text
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ORGANIZATION:
ANCHOR DARLING VALVE COMPANY WILLIAMSPORT, PENNSYLVANIA REPORT INSPECTION INSPECTION NO.-
99900053/82-01 DATE(S) 2/23-26/82 ON-SITE HOURS: 23 CORRESPONDENCE ADDRESS:
Anchor Darling Valve Company ATTN:
Mr. J. W. Marlatt General Manager 701 First Street Williamsport, PA 17701 ORGANIZATIONAL CONTACT:
Mr. G. W. Kneiser, Quality Assurance Manager TELEPHONE NUMBER:
(717) 323-6121 PRINCIPAL PRODUCT: ASME Section III Class 1, 2, and 3 valves.
NUCLEAR INDUSTRY ACTIVITY: Anchor Darling Valve Company's contribution to the nuclear industry represents approximately 70 percent of its total work load.
i n
/s M[af!8L ASSIGNED INSPECTOR:
/,
1 Wm. O. Kelley, Readtive & Cfponent Program Section
~
Da'te '
(R& CPS)
OTHER INSPECTOR (S):
APPROVED BY:
% / c-/W I. Barnes, Chief, R& CPS Date INSPECTION BASES AND SCOPE:
A.
BASES:
10 CFR Part 21 and 10 CFR Part 50, Appendix B.
B.
SCOPE:
This inspection was made as a result of the issuance of: (1) a con-struction deficiency report by Mississippi Power and Light Company concerning the premature opening of torque switches on valves installed at the Grand Gulf Nuclear Plant which resulted from engagement by excessively threaded stem protectors with the stem lock nuts; and (2) a potential 10 CFR Part 21 report by Pennsylvania Power and Light Company (PP&LC) concerning cavitation (cont. on next page)
PLANT SITE APPLICABILITY:
50-387, 50-416 8205030166 l
1 l
l ORGANIZATION:
ANCHOR DARLING VALVE COMPANY l
WILLIAMSIJRT, PENNSYLVANIA REPORT IN5PttiluN NO.:
99900053/82-01 RESULTS:
PAGE 2 of 4 l
l SCOPE: (Cont.) and/or difficulty in the throttling of valves F017A and B within the rar.ges specified in the PP&LC Technical Specification for the start up testing of the Susquehanna Steam Electric Station's Residual Heat Removal System.
Additional areas selected for inspection included design and document control, and status of previous inspection findings.
A.
VIOLATIONS:
None i
8.
NONCONFORMANCES:
None C.
UNRESOLVED ITEMS:
None D.
STATUS OF PREVIOUS INSPECTION FINDINGS:
1.
(Closed) Unresolved Item (81-01) - The inspector verified by review of the manufacturing drawings for the original valves installed in the Southern California Edison Company's San Onofre Nuclear Generating Station that the stacked tolerances were controlled during manu-facturing and assembly but were not in accordance with the clearances specified in the ADVC Design / Drafting Standard for quick closing valves.
The valves installed in the San Onofre Nuclear Generating Station were modified at the licensee's request to increase the closing speed and the ADVC standard was not developed until subsequent to this modifi-cation.
2.
(Closed) Nonconformance (81-01) - Two gate valves on Order No.
1024-001-001 for Washington Public Power Supply System Nuclear Project 2 were shipped with the by pass installed on the opposite side of the valves.
Ta inspector verified that the ADVC quality assurance program now requires separate travelers for valves that are identical with the exception of the by pass.
3.
(0 pen) Nonconformance (81-01) - An equation for a circular plate with inner edge fixed and supported and uniform loading along the outer edge was improperly used for analysis of a flange.
This item was not reviewed during this inspection as a result of corrective action correspondence being incomplete.
ORGANIZATION:
ANCHOR DARLING VALVE COMPANY WILLIAMSPORT, PENNSYLVANIA REPORT INSPECTION NO.:
99900053/82-01 RESULTS:
PAGE 3 of 4 E.
OTHER FINDINGS OR COMMENTS:
1.
10 CFR Part 21 Report by Pennsylvania Power and Light Company (PP&LC) -
l Problem reported was cavitation and/or difficulty in the throttling of valves F017A and B within the ranges specified in the PP&LC l
Technical Specifications for the start up testing of the Susquehanna Steam Electric Station's Residual Heat Removal System.
Valves F017A and B were purchased from ADVC by Bechtel Power Corpora-tion (BPC) on their purchase orders 8856P-10-A and 8856-12-A, dated December 26, 1973.
The flow requirement for the valves was specified in the Valve Data Sheets which were attached to the BPC valve speci-fications 8856P-10 & 12; however, the specifications did not require flow tests be performed on the valves.
ADVC's selection of their valves to meet the required flow rates was based on their calculated C factors.
y BPC's letter to ADVC dated May 6, 1981, listed the throttled flow condition for six valves during plant start-up and the duration (hours / year) of the throttled conditions.
These throttled flows were not specified in the original purchase documents.
ADVC evaluated the new flow conditions and advised BPC that two of the valves (Item 9.9 on purchase order number 8856P-12-A and item 7.11 on purchase order number 8856P-10-A) would require modification of the discs.
Subsequently, BPC issued Revision 24, dated November 11, 1981, to purchase order number 8856-10-A and Revision 29, dated December 4, 1980, to purchase order number 8856-12-A purchasing replacement throttling discs for the valves.
2.
Potential Construction Deficiency Report by Mississippi Power and Light Company (MP&LC) - Problem reported was the excessive threads on the valve stem protectors permitted the protectors to come in contact with the valve operator stem lock nut of the valves installed at the Grand Gulf Nuclear Plant, causing the valve operator opening torque switches to trip prematurely.
The Potential Construction Deficiency Report made by MP&LC to NRC Region II on March 3, 1980, identified two manufacturers whose stem protectors came in contact with the valve operator stem lock nuts, but did not identify the valves or the size and type of the Limitorque Corp. (LC) valve operators.
i l
l
ORGANIZATION:
ANCHOR DARLING VALVE COMPANY WILLIAMSPORT, PENNSYLVANIA HEFORI ANdetLitua NO.:
99900053/82-01 RESULTS:
PAGE 4 of 4 The NRC inspector verified by vist al observation of the LC valve operators (Models SMB-0, SMB-00, SM8-000, SMB-1, and SMB-2) and the LC catalog, that the valve operators had a thread run-out approximately 3/8 inch deep and a shoulder at the bottom of the run-out which would have prevented the pipe nipple or pipe plug (used as a stem thread protector or closure) from engaging the stem lock nut of the valve operators.
The LC valve operatoi Model SMB-3 has a 1 inch space from the bottom pipe thread to the lock nut.
This would mean that the pipe nipple used as a stem protector would have to have a running pipe thread in excess of 1 inches in length to engage the lock nut.
All of the LC valve operators inspected had their hand wheels mounted on the side of the operators, and there were no LC SMB-000 valve operators with the hand wheel mounted on the top of the operator available for inspection.
3.
Design and Document Control - Reviewed one section of the quality assurance manual, eight engineering standards, two customer specifi-cations, one customer purchase order, one master valve list, one material drawing list, one shop order instruction, one engineering data sheet, two valve assembly drawings, one design report, one design / drafting standard, and one flange design project.
Verified procedures had been implemented to control review and approval of design calculations.
PERSONS CONTACTED I
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