IR 05000266/1985013: Difference between revisions

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{{Adams
{{Adams
| number = ML20206P388
| number = ML20197H106
| issue date = 06/26/1986
| issue date = 05/14/1986
| title = Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-266/85-13 & 50-301/85-13.NRC Comments Made to Util During 860617 Discussion Summarized
| title = Discusses Safety Insp Repts 50-266/85-13 & 50-301/85-13 on 850722-26 & Forwards Notice of Violation.Violation Re Lack of Evaluation & Reportability of Auxiliary Feedwater Flow Transmitters Closed
| author name = Harrison J
| author name = Harrison J
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Line 10: Line 10:
| license number =  
| license number =  
| contact person =  
| contact person =  
| document report number = NUDOCS 8607020114
| document report number = NUDOCS 8605190062
| title reference date = 06-12-1986
| package number = ML20197H112
| package number = ML20206P391
| document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE
| document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE
| page count = 2
| page count = 2
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MAY 141986 Docket No. 50-266 Docket No. 50-301 Wisconsin Electric Power Company ATTN: Mr. C. W. Fay Vice President Nuclear Power Department 231 West Michigan, Room 308 Milwaukee, WI 53201 Gentlemen:
JUN 261986 Docket No. 50-266 Docket No. 50-301 Wisconsin Electric Power Company ATTN: Mr. C. W. Fay Vice President Nuclear Power Department 231 West Michigan, Room 308 Milwaukee, WI 53201 Gentlemen:
This refers to the special safety inspection (Inspection Report Nos.
Thank you for your letter dated June 12, 1986, informing us of the steps you have taken to correct the violations which we brought to your attention in our letter dated May 14, 1986. On June 17, 1986, a brief telephone discussion was conduted by Mr. A. S. Gautam of the Region III staff with Messrs. D. Blakely and M. Hanneman of your staff, with regard to Attachment 1 of your response.


The following sununarizes NRC conrnents made to your staff during the discussion.
50-266/85013 and 50-301/85013) conducted by Mr. R. C. Wilson and other NRC representatives on July 22-26, 1985, of activities at the Point Beach Nuclear Plant, Units 1 and 2, authorized by NRC Licenses No. DPR-24 and No. DPR-27, and to the discussion of our findings with Mr. C. W. Fay and other members of his staff at the conclusion of the inspection.


1.
The purpose of the inspection was to review the implementation of your EQ program in accordance with requirements of 10 CFR 50.49. During this inspection, four of these activities appeared to be in violation of NRC requirements, and were specified in Appendix A of our November 1, 1985, Report Nos. 50-266/85013 and 50-301/85013 as Potential Enforcement / Unresolved items. The enclosed Notice of Violation addresses two of these issues (50-266/85013-02(DRS);
50-301/85013-02(DRS) and 50-266/85013-03(DRS); 50-301/85013-03(DRS)) as violations of 10 CFR 50.49. A written response is required.


Item 50-266/_850_13_-02]DRS),;_50-301/8_5013-02_(DRS)
One of the remaining two items (50-266/85013-01(DRS); 50-301/85013-01(DRS)),
a.
concerning a lack of licensee evaluation and reportability of the auxiliary feedwater flow transmitters, has been addressed as part of item 50-266/85013-02(DRS); 50-301/85013-02(DRS), in the enclosed Notice of Violation.


Mitigatirt ;ircumstances, B (page 3, Attachment 1). Based on our reviews pt, formed by inspectors during the Point Beach EQ Audit, the NRC Audit Team concluded that prompt corrective action was not taken by the licensee in that the Unit 2 transmitters installed in 1981 were not qualified as of July 22, 1985, b.
This item was tracked as Item 50-266/85013-01(DRS);50-301/85013-01(DRS)and has been closed.


Mitigating Circumstances, D (page 3, Attachment 1). Since the affected transmitters were identified by the licensee as within the scope of 10 CFR 50.49, paragraph (b)(3), post accident instrumentation, these instruments are considered important to safety in that failure of these instruments could mislead an operator during a design basis accident.
Item 50-266/85013-04(DRS);50-301/85013-04(DRS)concerninganapparent lack of evidence that Limitorque DC operators, MS 2019 and 2020 were type tested in the same configuration as installed in the plant, is considered an Unresolved Item pending further review of the tested configuration.


2.
In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of this letter, the enclosures, and your response to this letter will be placed in the NRC Public Document Room.


Item 50-266/850_1_3_ _03(DRS); 50-301/85013_ _0_3(DRS)
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a.
8605190062 860514 PDR ADOCK O


Corrective Action (page 3, Attachment 1). The licensee did submit a Rockbestos report regarding the qualification of coaxial cable; however, this report was questioned by NRC Information Notice 84-44 and not accepted by the NRC at the time of the audit. Subsequently, Rockbestos perfortred additional testing which is the basis for the NRC acceptance of this cable.
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JUN 2 61986 Wisconsin Electric Power Company
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Wisconsin Electric Power


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MAY 14198S Company The responses directed by this letter and the accompanying Notice (Order)
are not subject to the clearance procedures of the Office of Management and Budget as required by the Paperwork Reduction Act of 1980, PL 96-511.


Mitigating Circumstances, B (page 4, Attachment 1). During the EQ audit, the licensee attempted to qualify the Rockbestos coaxial cable to NUREG 0588, Category 1, Section 2.3, which requires tests to be done on the same specimen. The cable was not qualified by analysis to 10 CFR 50.49(f)(4), as an extensive analysis would be required to address all aspects of the construction of a coaxial cable, c.
'
We will gladly discuss any questions you have concerning this inspection.


MitigatingCircumstances,D(page5, Attachment 1). The coaxial cable is considered important to safety as its failure would affect 10 CFR 50.49, paragraph (b)(3), post accident instrumentation, and could mislead an operator during a design basis accident.
Sincerely,
~'
Cri:inal SIPCd D' U U UWICO J. J. Harrison, Chief Engineering Branch Enclosure: Notice of Violation cc w/ enclosure:
J. J. Zach, Plant Manager DCS/RSB (RIDS)
Licensing Fee Management Branch Resident Inspector, RIII John J. Duffy, Chief Boiler Section Ness Flores, Chairperson Wisconsin Public Service Commission


We will examine these matters during a future inspection.
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Sincerely,
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Revision as of 12:52, 10 December 2024

Discusses Safety Insp Repts 50-266/85-13 & 50-301/85-13 on 850722-26 & Forwards Notice of Violation.Violation Re Lack of Evaluation & Reportability of Auxiliary Feedwater Flow Transmitters Closed
ML20197H106
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 05/14/1986
From: Harrison J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Fay C
WISCONSIN ELECTRIC POWER CO.
Shared Package
ML20197H112 List:
References
NUDOCS 8605190062
Download: ML20197H106 (2)
v • d • e


Text

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MAY 141986 Docket No. 50-266 Docket No. 50-301 Wisconsin Electric Power Company ATTN: Mr. C. W. Fay Vice President Nuclear Power Department 231 West Michigan, Room 308 Milwaukee, WI 53201 Gentlemen:

This refers to the special safety inspection (Inspection Report Nos.

50-266/85013 and 50-301/85013) conducted by Mr. R. C. Wilson and other NRC representatives on July 22-26, 1985, of activities at the Point Beach Nuclear Plant, Units 1 and 2, authorized by NRC Licenses No. DPR-24 and No. DPR-27, and to the discussion of our findings with Mr. C. W. Fay and other members of his staff at the conclusion of the inspection.

The purpose of the inspection was to review the implementation of your EQ program in accordance with requirements of 10 CFR 50.49. During this inspection, four of these activities appeared to be in violation of NRC requirements, and were specified in Appendix A of our November 1, 1985, Report Nos. 50-266/85013 and 50-301/85013 as Potential Enforcement / Unresolved items. The enclosed Notice of Violation addresses two of these issues (50-266/85013-02(DRS);

50-301/85013-02(DRS) and 50-266/85013-03(DRS); 50-301/85013-03(DRS)) as violations of 10 CFR 50.49. A written response is required.

One of the remaining two items (50-266/85013-01(DRS); 50-301/85013-01(DRS)),

concerning a lack of licensee evaluation and reportability of the auxiliary feedwater flow transmitters, has been addressed as part of item 50-266/85013-02(DRS); 50-301/85013-02(DRS), in the enclosed Notice of Violation.

This item was tracked as Item 50-266/85013-01(DRS);50-301/85013-01(DRS)and has been closed.

Item 50-266/85013-04(DRS);50-301/85013-04(DRS)concerninganapparent lack of evidence that Limitorque DC operators, MS 2019 and 2020 were type tested in the same configuration as installed in the plant, is considered an Unresolved Item pending further review of the tested configuration.

In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of this letter, the enclosures, and your response to this letter will be placed in the NRC Public Document Room.

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8605190062 860514 PDR ADOCK O

e i

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N> f o/

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Wisconsin Electric Power

MAY 14198S Company The responses directed by this letter and the accompanying Notice (Order)

are not subject to the clearance procedures of the Office of Management and Budget as required by the Paperwork Reduction Act of 1980, PL 96-511.

'

We will gladly discuss any questions you have concerning this inspection.

Sincerely,

~'

Cri:inal SIPCd D' U U UWICO J. J. Harrison, Chief Engineering Branch Enclosure: Notice of Violation cc w/ enclosure:

J. J. Zach, Plant Manager DCS/RSB (RIDS)

Licensing Fee Management Branch Resident Inspector, RIII John J. Duffy, Chief Boiler Section Ness Flores, Chairperson Wisconsin Public Service Commission

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RIII RIII RIII IE RI I RI(ITv'

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A9Q Sm(eegge QC Jy JwA Gautam/jk Muffett Potapovs Jack w Harri on 05/13/86 05/g/86 05/lA/86 05/ /86 05/p/86 05// '/86 i

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