ML19256F204
| ML19256F204 | |
| Person / Time | |
|---|---|
| Site: | Satsop |
| Issue date: | 10/31/1979 |
| From: | Renberger D WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | Spencer G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| Shared Package | |
| ML19256F203 | List: |
| References | |
| GO3-79-1892, NUDOCS 7912110471 | |
| Download: ML19256F204 (3) | |
Text
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P W shington Public Power Supply System A JOINT OPERATING AGENCY S
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o.<so.,avs.sooo October 31, 1979 G03-79-1892 Nuclear Regulatory Commission, Region V Suite 202, Walnut Creek Plaza 1990 N. California Boulevard Walnut Creek, California 94596 G,MhQ
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Attention:
Mr. G. S. Spencer b V M. C 'j p, b jm Chief Reactor Construction and
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Engineering Support Branch
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WPPSS NUCLEAR PROJECTS 3 AND 5 Q'N'"W'3 -j' NRC INSPECTION OF WNP-3 AND Wr1P-5 DOCKET NUMBERS 50-508 AND 50-509
Reference:
- 1) Letter, G. S. Spencer to N. O. Strand, same subject, dated August 28, 1979.
2)
Letter, D. F. Knuth to all AEC Licensees, ". Criterion for Determining Enforcement Action and Categories of Noncompliance", dated December 13, 1974.
Dear Mr. Spencer:
This letter is in response to your letter of August 28, 1979, which discussed the results of the inspection conducted August 27 through 30, 1979 of activities authorized by Nuclear Regulatory Commission Const; uction Permit Numbers CPPR-154 and CPPR-155. The letter identified two notices of noncompliance categorized in accordance with Reference 2, and required the Supply System to provide a res-ponse to these items.
The specific Nuclear Regulatory Commission Findings, as stated in your letter, and the Supply System responses are provided in Attach-ment I to this letter.
Should you have any questions or desire further information, please feel free to contact me directly.
Very truly yours,
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Renbe ger Assistant Director, Technology Attachment cc:
D. Smithpeter, BPA
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JG Davis, Director, NRC, Washington, D.C.
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ATTACHMENT I Nuclear Regulatory Commission Finding 10 CFR 50, Appendix B, Criterion V, as implemented by Section 17.1.5 of the Quality Assurance Program documented in the PSAR and the WPPSS QA Program Manual Procedure QAP-2, Paragraph 3.1, states, in part, that, " Activities affecting quality...shall be accomplished in accor-dance with... instructions, procedures, or drawings."
Chicago Bridge and Iron Welding Procedure Specification No. WPS-E7018/
74-3431 stages that " Plate thicknesses over 1" require a continuous pre-heat of 200 F minimum."
Contrary to the above requirement, on August 27, 1979, the NRC inspector observed that while welding was in progress, the preheat temperature of seamC-1,materialthicknessof2-5/f6",ontgebottomheadofthgUnit3 containmentvesselbetweegabout270 and 360, was less than 200 F as indicated by use of a 200 F Templistick.
Corrective Actions Taken:
The CB&I Welding and QA Manager initiated NCR 605 for the stated condi-tion. An fnvestigation determined that the preheat had not dropped as low as 100 F.
The NCR was evaluated by Engineering and dispositioned as " Accept As Is" because both the ASME Coge Section IX and the CB&I welding specification allows a drop of 100 F below preheat requirements without need for requalifying the procedure. The preheat system was modified to -prevent decreases in gas pressure and preheat is being checked by welders to assure it complies with requirements.
The CB&I Project Superintendent, welding supervisors, pushers and welders were instructed concerning preheat maintenance and monitoring.
CB&I welding is now in compliance with all weld preheat requirements.
Nuclear Regulatory Commission Finding:
10 CFR 50, Appendix B, Criterion V, as implemented by Section 17.1.5 of the Quality Assurance Program documented in the PSAR and the WPPSS QA Manual Procedure QAP-2, Paragraph 3.1, states, in part, that, "Acti-vities affecting quality...shall be accomplished in accordance with...
instructions, procedures, or drawings."
Morrison-Knudsen Procedure No. CP-15-WPPSS, " Field Fabrication of Rein-forcing Steel", Paragraph 8.1 states, in part, that "MK QC shall verify that heat numbers have been transferred to the metal tags attached to field fabricated rebar..."
Morrison-Knudsen Procedure No. CP-ll-WPPSS, " Reinforcing Steel Instal-lation and Inspection", Paragraph 8.5 states that "Resteel shall be supported from the ground in such a manner to allow adequate ground clearance." Paragraph 10.9 states that, "Rebar shall be used in such 1653 193
Attachment I Page 2 a sequence so that the last bar remaining in a bundle is a tagged bar
... Broken bundles shall be resecured vaen bars for immediate use have been removed." Paragraph 11.2 states, in part, that "During resteel erection, the Morrison-Knudsen Quality Control Inspector...will inspect the following items... continuous monitoring is performed to ascertain that the last rebar from bundle has metal identification tag attTched."
Contrary to the above, on August 27, 1979, the NRC Inspector observed the following conditions in the Unit No. 3 Rsactor Auxiliary Building at Elev. 335:
(1) One bundle #6 field-fabricated reinforcing steel had no. heat number tag.
(2) One bundle #6 owner-furnished reinforcing steel had no identifi-cation tag.
(3) Two #11 owner-furnished reir. forcing steel bars were not supported above the concrete and were laying in water. The identification tags were also missing.
(4) A length of #11 and a length of #8 reinforcing steel had no identification tags.
Corrective Actions Taken:
The subject reinforci'.g steel was investigated, placed on hold and removed from the area. Storage was brought into compliance. The con-tractors specification was reviewed and modified to assure that the PSAR identification and storage requirements were being met.
The storage and identity of reinforcing steel is now in full compliance with PSAR and procedural requirements.
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