Responds to Re Constituent GL Johnson Safety Concerns Expressed in 890515-17 Ltrs to Lw Zech.Nrc Takes Nuclear Safety Very Seriously & Will Bring Technical & Investigative Resources to Bear in Resolving Concerns
B17851, Forwards Semiannual fitness-for-duty Program Performance Data for 990101-990630 for Millstone Nuclear Power Station, Units 1,2 & 3,IAW 10CFR26.71(d)
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B17838, Forwards Revs 34 & 35 to Physical Security Plan.Explanation of Changes Provided as Attachment 1.Without Encls
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B17872, Informs of Election to Consolidate Previous Commitments Re Work Observation Program with Two New Programmatic Commitments Listed in Attachment 1
B17859, Forwards up-to-date Distribution Lists for NRC Correspondence to NNECO & NUSCO.Side-bars Indicate Changes from Previous Lists Provided to NRC on 980128
B17881, Forwards NRC Form 398 & NRC Form 396 for Le Olsen,License SOP-10398-2.Encl Withheld Per 10CFR2.790(a)(6)
B17882, Forwards NRC Forms 398 & 369 in Support of License Renewal for Bb Parrish,License SOP-10399-2.Encl Withheld Per 10CFR2.790(a)(6)
B17880, Forwards NRC Form 398 & NRC Form 396 for Rf Martin,License SOP-10397-0.Encls Withheld Per 10CFR2.790(a)(6)
B17876, Informs That Util Will Adopt Last Approved Northeast Util QA Program (Nuqap) Tr,Rev 21,dtd 990630,as Unit 1 Nuqap,Per Decision to Permanently Cease Operations at Subject Plant
B17865, Provides NRC Staff with Updated Proposed Rev of FSAR Section 14.6.3, Radiological Consequences of SG Tube Failure. Updated Proposed Rev Will Replace Info Provided in Attachment 3 of Initial Submittal
B17867, Requests Relief from Requirements of 10CFR50.55a(g),IAW ASME Section XI for Millstone,Unit 3.Util Requests Relief from Performing Visual Exam of Reactor Pressure Supports to Extent Required by Code for Class 1 Supports
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B17884, Forwards NRC Form 536, Operator Licensing Exam Data, for Mnps,Units 2 & 3,per Administrative Ltr 99-03
B17888, Informs That There No Longer Exists Need to Maintain Millstone Unit 2 SRO License for CA Hines,License SOP-10741-01,effective 990915
B17890, Provides Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal
B17887, Requests Exemption from Requirements of 10CFR140.11(a)(4) Which Requires Licensees to Maintain Secondary Financial Protection Beyond Primary Layer
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B17892, Requests Withdrawal of License Amend Application Re 24-month SG Tube Insp Surveillance Extensions,Submitted in Util 950726 & s to NRC
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B17900, Forwards Revised Assumptions Used in Fuel Handling Accident Analysis & Summary of Results.List of Regulatory Commitments Are Listed in Attachment 1
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B17886, Requests Permission to Utilize Code Case N-623, Deferral of Insps of Shell-to-Flange & Head-to-Flange of Reactor Vessel,Section Xi,Div 1, for Millstone Unit 2
B17901, Submits Statement of Personal Qualification (NRC Form 398) Along with Supporting Certification of Medical Exam by Facility Licensee (NRC from 396) in Support of License Renewal for PM Miner.Encls Withheld,Per 10CFR2.790(a)(6)
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DD-99-12, Informs That Time Provided by NRC Regulation within Which Commission May Act to Review DD-99-12 Has Expired.With Certificate of Svc.Served on 991028
DD-96-23, Informs That on 961226,NRC Issued Partial Directors Decision DD-96-23,in Response to Petition Submitted,Per 10CFR2.206,on 950821
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DD-99-12, Informs That Time Provided by NRC Regulation within Which Commission May Act to Review DD-99-12 Has Expired.With Certificate of Svc.Served on 991028
-1 The Honorable Christopher J. Dodd United States Senator 1
Putnem Park 100 Great Meadow Road Wethersfield, Connecticut 06109
Dear' Senator Dodd:
i Thank you for your letter dated May 26, 1989, regarding the safety concerns expressed by Mr. Gary L. Johnson, your constituent, in his letters to you and lo:
to NRC Chairman Lando W. Zech, Jr. dated May 17 and 15,1989 respectively, Mr. Johnson's concerns and the concerns of other employees at the Millstone i
plant were brought to the attention of the NRC Region I staff in 1988. The concerns were processed through NRC's Allegation Management System, which provides for a thorough review and inspection of all issues of nuclear safet/
)
brought to the NRC by concerned individuals. The system also provides that individuals be apprised of the results of our evaluation and resolut?on of their! concerns.
Mr. Johnson's concerns were investigated by our inspection staff and also were referred to the licensee. We requested that the licenseo review its allegation management system and Mr. Johnson's concerns. We provided the results of our evaluation in a letter to Mr. Johnson dated June 7,'1988, and in an accompanying Inspection Report 50-336/88-07. Region I staff has cutinued to follow up this matter after receiving a reply from Mr. Johnsen dated August 15, 1988, in which he expressed dissatisfaction with our findings. Subsequently, Mr. Johnson addressed his concerns in a letter to NRC Chairman Lkndo W. Zech, Jr.,
' dated May 15, 1983.
With regard to Mr. Johnson's allegations concerning the calibration of instruments at Millstone Unit 2, we intend to conduct a special inspection by an evaluation team involving joint participation by the NRC Office of Nuclear Reactor Regulation and the NRC Region I office. This team will visit Millstone, conduct interviews, and inspect open technical issues associatea with l
Mr. Johnson's allegations and the allegmons of other people. Mr. Johnson was informed of these plans to resolve his concerns in our letter dated June 7,
1989, a copy of which is enclosed herein. We will send you a copy of the inspection report documenting the results of the special inspection when it is completed. Should we find that any s5fety requirements have been vielated at Millstone, we will handle these violations in accordance with our enforcement policy.
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The Honorable Christopher J. Dodd ^
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In closing, I: assure you that we take nuclear safety very !,eriously and we willbring our technical and investigative resources to bear in resolving Mr.' Johnson's concerns.