ML20036B462
| ML20036B462 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/19/1991 |
| From: | Wenzinger E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | AFFILIATION NOT ASSIGNED |
| Shared Package | |
| ML20036A053 | List:
|
| References | |
| FOIA-92-162 NUDOCS 9305200251 | |
| Download: ML20036B462 (2) | |
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JUL 191991 l
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The NRC Region I office has completed its followup of a concern that you brought to our attention on June 17,1991, asserting complaints regarding violations of SP-EE-076, a standard i
specification for electrical installations.
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Jur resolution of this concern was previously documented to you in letters dated June 13,1989, and March 5,1991, copy attached. We consider this matter both unsubstantiated and closed.
Again, the reason this issue is unsubstantiated is that you have not provided documented evidence that compliance with explicit provisions of SP-EE-076 is required in the conduct of i
i activities at Millstone Unit 2.
We appreciate you informing us of your concerns and feel that we have been responsive to those j
concerns. Should you have any additional questions regarding these matters, please call me l
collect at (215) 337-5225.
Sincerely; Original Sig.d Br Edward Wenzinger, Chief Reactor Projects Branch 4 Attachments: As stated l
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Docket No. 50-336
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File No. RI-A-88-0003 (B.16.01) j j
Subject:
Allegation Concerning Millstone Unit 2 The NRC Region I of fice has completed its followup in response to the concerns You expressed dissatisfaction you brought to our attention on November 1,1989.
with the NRC followup and disposition of allegations, specifically the NRC inspection teams disposition of your concerns relating to the Sp-EE-076 Electric l
Code and the use of electrical metallic tubing (EMT), as documented in inspection report 50-336/89-13.
The NRC has subsequently reviewed your concerns again and concluded that the 50-336/89-13 evaluation and disposition of your concerns in inspection report was correct.
I The inspection team determined that Sp-EE-076, as a specification, does not It is a specification developed by Stone and Webster and used apply to Unit 2.
in the construction of M111 stone t' nit 3, the plant for which Stone and Webster was the architect and engineer. SP-EE-076 has been distributed to the other nuclear generating stations operated by the licensee as a reference and general The inspection team reviewed licensee internal memoranda guidance document.
that promulgated the use of SP-EE-076 at these plants, and no discrepancies were noted.
The inspection team also concluded that your allegation that ENT is used in applications other than lighting installations at Millstone Unit 2 is substantiated. These applications, however, are clearly allowed for and controlled by the applicable specification, Bechtel drawing 25203-34001, and, therefore, pose no safety hazard to the plant.
We appreciate your informing us of your concerns and feel that our actions in this matter have been responsive to those concerns. Should you have any additional questions, or if I can be of further assistance in this matter, please call me collect at (215) 337-5120.
Sincerely,
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Reactor Projects Sec' tion (A W. Raymond l
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{'*@T KING OF PRUStlA. PENNtYLVANIA 19404 WAR 0 51991 The NRC Region I has completed its followup of the concerns that you brought to our our attention by way of memoranda dated October 7, September 29, and October I
alleging (1) procedural non-compliance with SP-EE-076, (2) a technical specificat violation during instrument and controls troubleshooting, (3) an improper tagout during maintenance, and (4) a failure to comply with procedural requirements during fuel movem I
With regard to issue (1), we have previously dccumented our review of this item in an 13,1990 (attached). We inspection repon 50-336/8913 and in a letter to you dated June f
consider this matter both unsubstantiated and closed. The reason tf is that you have not provided documented evidence that compliance with explicit of SP-EE-076 is recuired in the conduct of activities at Millstone Unit 2.
J With regard to issue (2), you alleged that no diesel generator power source was ava during the maintenance. We documented our review of this item in inspection r 90-22, section 5.1.2 (attached). As documented in our report, emergency power was available from a number of sources including manual stan of the affected diesel generator.
Having only one diesel available by manual start is a condition allowed during refueling Millstone Unit 2. Your allegation is therefore unsubstantiated. We consider this matter closed.
With regard to issue (3), you alleged that maintenance was performed on the "A* steam generator feedwater regulating valve with an improper tagout. We reviewed this section 5.1.1 (attached). We found that all required inspection repon 50-336/90-22, documentation and authorizations were used in the electrical isolation. Your allegation was therefore unsubstantiated and we consider this matter closed.
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With regard to issue (4), you alleged that a direct violation of procedures occurred during fuel movement. We reviewed this allegation in inspection report 50-336/90-22, section 9.8 i
(attached), and found that the procedure was adhered to during the operations however some l
additional procedural detail may have prevented the problem.. Your allegation was therefol unsubstantiated and we consider this matter closed.
Should you have any additional questions or if I can be of further assistance in these matt t
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please call me collect at (215) 337-5225.
i Sincerelyy 1b Edward denzinger, hie I
Reactor Projects Bran 4
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