Letter Sequence Meeting |
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Results
Other: ML19254E990, ML19261B262, ML19261B350, ML20023B885, ML20024F311, ML20062G268, ML20093C407, ML20101Q731, ML20127C328, ML20129J045, ML20134A118, ML20134A133, ML20134A144
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MONTHYEARML19261B3501978-07-11011 July 1978 Forwards App 1 Model Tech Specs Intended to Provide Guidance Re Equipment & Administrative Requirements Specs.Requests Submittal of License Amend Application Reflecting Applicable Specs.W/O Encl Project stage: Other ML20244A4331978-08-28028 August 1978 Summary of Meeting on 780815 Re Util Plans to Submit License Amend Application to Implement App I Tech Specs for Facility Project stage: Meeting ML20244A4271978-08-29029 August 1978 Forwards Summary of 780815 Meeting Re Subj Facility Tech Specs Project stage: Meeting ML20062G2681978-12-21021 December 1978 Forwards Proposed Amends to Tech Specs & to Environ Tech Specs of Subj Facils,Minus Section on Solid Radioactive Waste Which Is Still Under Dev.Requests Delay of Implementation to 790701 or Later Pending Review Completion Project stage: Other ML19261B2621979-01-29029 January 1979 Requests Addl Info Re Requirements for Solidification & Proposed Radiological Effluent Tech Specs.Requests Info within 30 Days of Receipt of Ltr Project stage: Other ML19283B7861979-03-19019 March 1979 Util Believes NRC Erred in Requesting Payment of $5,600 Fee for Proposed Changes to Tech Specs.Forwards Fee & Reserves Right to Request an Exemption & Refund Per 10CFR170.22 Project stage: Request ML19270F9591979-03-22022 March 1979 Summary of 790316 Meeting W/Ga Power Co in Bethesda,Md Re Radiological Effluent Specs Project stage: Meeting ML19254E9901979-10-30030 October 1979 Commits to Provisions of Tech Spec 3.11.4 of Radiological Effluent Tech Specs,Revision 2.Necessary Procedures for Compliance Will Be Implemented by 791201 Project stage: Other ML20028F6911983-01-31031 January 1983 Notification of 830223-24 Meetings W/Util,Eg&G & Scsi in Atlanta,Ga to Discuss NRC Questions Re Review of Licensee Radiological Effluent Tech Spec Submittal Project stage: Meeting ML20023B3581983-04-0404 April 1983 Forwards List of Major Radiological Effluent Tech Spec Items from Licensee Proposal That Were Not Resolved at Atlanta Meeting.Differences Between Unit 1 & Unit 2 Proposals Are Minor.Commitment Date for Next Submittal Not Identified Project stage: Meeting ML20151H6481983-04-22022 April 1983 Summary of 830223-24 Meetings W/Util & Eg&G in Atlanta,Ga Re Proposed Radiological Effluent Tech Specs Project stage: Meeting ML20023B8851983-04-22022 April 1983 Forwards Eg&G Transmitting List of NRC Comments on Unresolved Items from Proposed Radiological Effluent Tech Specs.Earlier Scheduled Date for Final Submittal Requested Project stage: Other ML20024F3111983-08-30030 August 1983 Advises That NPDES Permit Ga 004120 Renewed,Effective 830801,w/expiration Date of 871205.Change Will Be Reflected in Proposed Radiological Tech Specs Scheduled for Submittal in Sept 1983 Project stage: Other ML20080Q1511983-10-0606 October 1983 Application for Amend to Licenses DPR-57 & NPF-5 Revising Tech Specs by Transferring Radiological Effluent Tech Specs from App a to App B,Per 781221 submittal.Marked-up Tech Specs Encl Project stage: Request ML20085L0881983-10-17017 October 1983 Application for Amend to Licenses DPR-57 & NPF-5 Transferring Radiological Effluent Tech Spec from App B to App a Project stage: Request ML20094H2761984-08-0101 August 1984 Application for Amend to Licenses DPR-57 & NPF-5,revising Radiological Effluent Tech Specs (RETS) by Transferring RETS from App B to App a & Including Editorial & Administrative Changes & Changes Based on NRC Comments Project stage: Request ML20093C4071984-10-0101 October 1984 Proposed Tech Specs,Correcting Technical Inaccuracies Re Trip Function Associated W/Instrument,Doses Averaged Over Elapsed Quarter Rather than Projected for Remaining Quarter & Bases for Explosive Gas Mixture Spec Project stage: Other ML20093C3891984-10-0101 October 1984 Application to Amend Licenses DPR-57 & NPF-5,correcting Technical Inaccuracies Re Trip Function Associated W/Instrument,Doses Averaged Over Elapsed Quarter & Bases for Explosive Gas Mixture Spec Project stage: Request ML20127C3281984-11-30030 November 1984 Radiological Effluent Tech Specs Implementation - Ei Hatch Nuclear Plant Units 1 & 2, Informal Rept Project stage: Other ML20101Q7311985-01-0202 January 1985 Advises That Schedule for Implementation of Radiological Effluent Tech Specs (RETS) Modified Due to Substantial Differences in Reporting Criteria.Rets Will Be Implemented at First Semiannual Period Following NRC Issuance Project stage: Other ML20128L2201985-06-27027 June 1985 Safety Evaluation Supporting Amends 109 & 47 to Licenses DPR-57 & NPF-5,respectively Project stage: Approval ML20134A1181985-06-27027 June 1985 Reissued Amends 109 & 47 to Licenses DPR-57 & NPF-5, Respectively,Reflecting Corporate & Plant Staff Reorganization & Deleting Senior Reactor Operator License Requirement for Plant Manager Project stage: Other ML20134A1441985-06-28028 June 1985 Reissued Amends 110 & 48 to Licenses DPR-57 & NPF-5, Respectively,Adding Proposed Radiological Effluent Tech Specs to App a & Deleting Radiological Tech Specs Project stage: Other ML20129J0451985-06-28028 June 1985 Amends 110 & 48 to Licenses DPR-57 & NPF-5,respectively, Adding Radiological Effluent Tech Specs (App a) to Licenses & Deleting Radiological Tech Specs from App B Project stage: Other ML20129J0491985-06-28028 June 1985 Safety Evaluation Supporting Amends 110 & 48 to Licenses DPR-57 & NPF-5,respectively Project stage: Approval ML20134A0971985-08-0202 August 1985 Forwards Reissued Amends 109 & 47 to Licenses DPR-57 & NPF-5,respectively & Safety Evaluation.Amends Revise Tech Specs to Reflect Corporate & Plant Staff Reorganization to Change Composition of Plant Review Board Project stage: Approval ML20134A1331985-08-0202 August 1985 Forwards Reissued Amends 110 & 48 to Licenses DPR-57 & NPF-5,respectively,adding Proposed Radiological Effluent Tech Specs to App a & Deleting Radiological Tech Specs from App B Project stage: Other 1983-10-06
[Table View] |
Forwards List of Major Radiological Effluent Tech Spec Items from Licensee Proposal That Were Not Resolved at Atlanta Meeting.Differences Between Unit 1 & Unit 2 Proposals Are Minor.Commitment Date for Next Submittal Not Identified| ML20023B358 |
| Person / Time |
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| Site: |
Hatch  |
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| Issue date: |
04/04/1983 |
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| From: |
Serrano W EG&G, INC. |
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| To: |
Willis C NRC |
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| Shared Package |
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| ML20023B361 |
List: |
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| References |
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| TAC-08043, TAC-08095, TAC-8043, TAC-8095, NUDOCS 8304220257 |
| Download: ML20023B358 (3) |
|
Similar Documents at Hatch |
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Text
..
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e Enclosure 11
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E Gr G u...
II P.O. BOX 1625, ICAHO FALLS, IDAHO 83415 d
1
.l April 4, 1983 2
"r.
C. A. Willis Mail Stop P-730 Phillips Building U.S. Nuclear Regulatory Commission s
Washington, D. C.
20555 UNRESOLVED ITEMS FROM HATCH RETS REVIEW - Serr-9-83
Dear Mr. Willis:
Attached is a listing of the major RETS items from the Hatch Unit 1 proposal that were not resolved at the Atlanta meeting. Althou5h the Hatch Unit 2
{
" proposal was not discussed, the differences between the Unit 1 and Unit 2 j
proposals are minor and the attached listing applies to both units.
I The ODCM (prepared in 1978) was not reviewed at the plant visit since the A
Licensee preferre;f to resubmit another ODCM. Also a PCP has not been wbmitted for review.
A commitment date for the next submittal was not identified at the meeting.
l Sincerely yours,
...a W. Serrano Radiation. Measurer.ent Programs Branch I
jd
Attachment:
As stated cc:
W. W. Meir.ke, hRC G. L. Vivian, DOE-ID R. W. Kiehn, EG&G Idaho XA Copy Hos Been Sent to PDR x
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liATCH UNIT NO. I q
Nunber*
flVREG-0473 HATCH Comment 16 T'able 4.14.1-1 A differential pressure gauge Item 4 measures thedP between the
'i Service Water System and the Closed Cooling Water System.
The gauge should provide alarm j
or some other indication when theAP is out of ' limit and
{
these functions should be
- j periodically checked. The proposal does not...clude a channel functional test in the q
surveillance requirenents.
48 Table 4.11-2 Table 4.15.2-1 Table 4.15.2-1 does not include Iten B a requirement to sample prior
-ii to a drywell purge. The con-tainment effluents are released j
through the standby gas treat-ment system. At the site visit
~
it was learned the releases can be through either a 2-inch line
-l 2r an 18-inch line.
It was j
suggested that when releases are l
through the 18-inch line that the monitors of Table 3.2-10 be on line and a grab sample be
~
analyzed prior to release.
q' i
. Table 4.15.2-1 The LLD value' for the noble gas
. 50 Table 4.11-2 item 0 monitors was not identified in the table. The Licensee states l
the values are detailed in the n
FSAR.
Table 4.11-1 Table 4.15.1-1 The proposal uses !!inir:um Detectable Concentration (MDC) instead of LLD.
0 Reference is to the review question in letter DHA-ll-82 dated t
[
Movember 23', 1982.
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f!UREG-0473 HATCil Corament 71 Table 3.12-1 Table 3.16-1 The proposal does not include 4
Item 3b Iten 3b the requirement for a gamma isotopic analysis on ground water samples.
i.;
81 3.12.2
-3.16.2 The Land Use Census does not 3
state it will identify and report all gardens of greater I
2 than 500 ft,
,a iiq lJ 91 6.5.2.8.0 6.5.2.8.1 It is not clear that the I
model RETS QA requireinents
.I l
for environmental monitoring are being satisfied by Speci-li fication 6.5.2.8.1.
1:
100 6.13 6.15' A Specification addressing the Process Control Program uas not included.
This was i
unresolved at the meeting.
101 6.15 6.17 A Specification on major
(
changes to radioactive waste l
treatment systems was not included in the proposal. The Licensee states the requirements are included in 10 CFR 50.59.
Li llowever, it was stated that I
10 CFR 50.59 did not include the radwaste systems.
This was unresolved at the meeting.
- i t
-l R
[j Reference is to the review question in letter DWA-ll-82 dated L.l' flovember 23, 1982.
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