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| | number = ML20128G870 | | | number = ML20128G870 |
| | issue date = 05/20/1985 | | | issue date = 05/20/1985 |
| | title = Forwards Comments on Offsite Dose Calculation Manual Submitted by 850228 Ltr.Revised Manual Resolving Staff Comments Requested | | | title = Forwards Comments on Offsite Dose Calculation Manual Submitted by .Revised Manual Resolving Staff Comments Requested |
| | author name = Youngblood B | | | author name = Youngblood B |
| | author affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) | | | author affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) |
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| | contact person = | | | contact person = |
| | document report number = NUDOCS 8505300338 | | | document report number = NUDOCS 8505300338 |
| | | title reference date = 02-28-1985 |
| | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE | | | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE |
| | page count = 13 | | | page count = 13 |
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| ==Subject:== | | ==Subject:== |
| NRC Staff Coments on the Offsite Dose Calculation Manual for the Perry Nuclear Power Plant, Unit 1 The staff hcs completed its initial review of the Offsite Dose Calculation Manual (0DCM) submitted by your letter dated February 28, 1985 and its specific comments on the ODCM are enclosed. It is requeste'd that your staff submit a revised ODCM that resolves the staff's comments. Should your staff wish to discuss the enclosed comments, please advise the Perry Project Natiager, John Stefano, accordingly so that appropriate arrangements can be scheduled. | | NRC Staff Coments on the Offsite Dose Calculation Manual for the Perry Nuclear Power Plant, Unit 1 The staff hcs completed its initial review of the Offsite Dose Calculation Manual (0DCM) submitted by your {{letter dated|date=February 28, 1985|text=letter dated February 28, 1985}} and its specific comments on the ODCM are enclosed. It is requeste'd that your staff submit a revised ODCM that resolves the staff's comments. Should your staff wish to discuss the enclosed comments, please advise the Perry Project Natiager, John Stefano, accordingly so that appropriate arrangements can be scheduled. |
| Sincerely, B. J. Youngblood, Chief Licensing Branch No. 1 Division of Licensing | | Sincerely, B. J. Youngblood, Chief Licensing Branch No. 1 Division of Licensing |
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| NRC Staff Coments on the Offsite Dosa Calculation Manual i _ for the Perry Nuclear Power Plant,- Unit 1 | | NRC Staff Coments on the Offsite Dosa Calculation Manual i _ for the Perry Nuclear Power Plant,- Unit 1 |
| ~ | | ~ |
| [ The staff has completed its initial review of the Offsite Dose Calculation Manual (0DCM) submitted by your letter dated February 28, 1985 and_its spacific | | [ The staff has completed its initial review of the Offsite Dose Calculation Manual (0DCM) submitted by your {{letter dated|date=February 28, 1985|text=letter dated February 28, 1985}} and_its spacific |
| , . consents 'on the ODCM are enclosed. It is requested that your staff submit a revised ODCM that. resolves the staff's comments. Should your staff wish to discuss the enclosed comments, please advise _the Perry Project Manager, John Stefano, accordingly so that appropriate arrangements can be scheduled. | | , . consents 'on the ODCM are enclosed. It is requested that your staff submit a revised ODCM that. resolves the staff's comments. Should your staff wish to discuss the enclosed comments, please advise _the Perry Project Manager, John Stefano, accordingly so that appropriate arrangements can be scheduled. |
| Sincerely, g/4. w;ba B. J. Youngblood, Chief Licensing Branch No. I Division of Licensing | | Sincerely, g/4. w;ba B. J. Youngblood, Chief Licensing Branch No. I Division of Licensing |
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Category:CORRESPONDENCE-LETTERS
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[Table view] Category:NRC TO UTILITY
MONTHYEARML20058H6511990-11-14014 November 1990 Forwards Maint Team Insp Rept 50-440/90-12 on 900917-21 & 1001-05 & Notice of Violation ML20058E7141990-10-30030 October 1990 Forwards Exam Forms & Answer Keys,Grading Results & Individual Answer Sheets for Each Applicant ML20058D6001990-10-29029 October 1990 Requests Util Provide Ref Matls Listed in Encl 1, Ref Matl Requirements, for Licensing Exams Scheduled for Wk of 910218 ML20058D5141990-10-26026 October 1990 Requests That Util Furnish Items Listed in Encl 1, Ref Matl Requirements, for Requalification Program Evaluation Scheduled for Wk of 910211 ML20058D2081990-10-19019 October 1990 Forwards Safety Insp Rept 50-440/90-18 on 900730-0919 & Notice of Violation ML20062A8631990-10-15015 October 1990 Forwards Safety Insp Rept 50-440/90-19 on 900905-21.No Violations Noted DD-90-06, Forwards Director'S Decision DD-90-06 Dtd 900925,for Info1990-09-27027 September 1990 Forwards Director'S Decision DD-90-06 Dtd 900925,for Info ML20059M2101990-09-25025 September 1990 Forwards Info Re Generic Fundamentals Exam Section of Operator Licensing Written Exams to Be Administered on 901010,including Map of Area Where Exams Will Be Taken, Preliminary Instructions for Exam & Equation Sheet ML20059L1571990-09-0707 September 1990 Forwards Exam Rept 50-440/OL-90-02 on 900806.Answer Key & Facility Comment Resolution Also Encl ML20059G8791990-08-29029 August 1990 Requests Final Analysis of Plant Combustible Gas Control Sys Addressing Key Elements Identified in Encl Ser,Section 8.0 Re Mark III Containment Hydrogen Control by 910301 ML20059B4801990-08-22022 August 1990 Forwards Safety Insp Rept 50-440/90-13 on 900625-0802 & Notice of Violation ML20058N4921990-08-0808 August 1990 Forwards Safety Insp Rept 50-440/90-16 on 900709-13.No Violations Identified ML20058M6141990-08-0707 August 1990 Forwards Sample Registration Ltr for 901010 Generic Fundamentals Section of Written Operator Licensing Exam. 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Changes Included Refined Criteria for Declaring Onsite Recovery Phase of Operations & Downgraded Classification ML20246Q0191989-07-14014 July 1989 Forwards Safety Evaluation Re Updated SAR App 1B Commitments.Commitments Relates to Upgrading of Neutron Monitoring Instrumentation Per Reg Guide 1.97,Revision 2, Instrument Setpoint Methodology & Gaseous Effluent .. ML20246H9411989-07-11011 July 1989 Forwards Insp Rept 50-440/89-11 on 890320-0419 & Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $37,500 ML20246D9551989-07-0606 July 1989 Forwards Safety Insp Rept 50-440/89-14 on 890425-27 & 0620. No Violations Noted ML20245L1081989-06-28028 June 1989 Forwards Enforcement Conference Rept 50-440/89-20 on 890607 Insp Rept 50-440/89-16 on 890502-0602 & Notice of Violation. Concerns Raised That Appropriate Radiation Surveys Not Made & That wk-old Survey Used for Initial Entry ML20245G1121989-06-22022 June 1989 Forwards Safety Insp Rept 50-440/89-07 on 890309-0605 & Notice of Violation ML20245B6351989-06-19019 June 1989 Forwards Safety Insp Rept 50-440/89-15 on 890515-0608.No Violations Noted ML20244D8791989-06-0808 June 1989 Ack Receipt of Containing Description of Scope & Objectives for 1989 Plant Exercise Scheduled for 890830.No Concerns W/Proposed Scope & Objectives Noted ML20244D6191989-06-0707 June 1989 Forwards Safety Evaluation Accepting Licensee 840406 Response to Generic Ltr 83-28,Item 4.5.3 Re Confirmation That on-line Functional Testing of Reactor Trip Sys Being Performed at Plant ML20244C2251989-06-0505 June 1989 Forwards Safety Insp Rept 50-440/89-16 on 890502-0602. Violations Noted.Decision Re Enforcement Action Will Be Made Following 890607 Enforcement Conference in Region III Ofc ML20247M1311989-05-31031 May 1989 Ack Receipt of Util 880711 Response to NRC Bulletin 88-004, Potential Safety-Related Pump Loss. Demonstration of How Operators Would Control RCIC Pump Operation During All Expected Operating Occurrences IR 05000440/19890161989-05-26026 May 1989 Confirms 890519 Plans to Conduct Enforcement Conference on 890607 to Discuss Violations Noted in Insp 50-440/89-16 ML20247J0331989-05-23023 May 1989 Forwards Director'S Decision,Transmittal Ltr & Fr Notice in Response to Ocre 10CFR2.206 Petition Expressing Concerns Re 880309 Power Oscillation Event at Facility.Petitioner Request Being Treated as Petition for Rulemaking IR 05000440/19870251989-05-23023 May 1989 Grants Request for 6-month Extension Until 891031 to Fulfill Commitment to Computerize Reliability Info Tracking Sys Per Violations Noted in Insp Rept 50-440/87-25 ML20247E7201989-05-18018 May 1989 Forwards Enforcement Conference Rept 50-440/89-18 on 890511 Re Violations Noted in Insp Rept 50-440/89-11 1990-09-07
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217F3901999-10-14014 October 1999 Discusses Request That Proprietary Document NEDE-32907P,DRF A22-0084-53, Safety Analysis Rept for Perry NPP 5% Power Uprate, Class III Dtd Sept 1999 Be Withheld.Determined Document Proprietary & Will Be Withheld ML20217G9201999-10-14014 October 1999 Discusses Utils Request for Approval of Quality Assurance Program Changes ML20212K9271999-09-30030 September 1999 Refers to 990927 Meeting Conducted at Perry Nuclear Power Plant to Discuss Initiatives in Risk Area & to Establish Dialog Between SRAs & PSA Staff ML20212J1451999-09-30030 September 1999 Forwards Order,In Response to 990505 Application PY-CEI/NRR- 2394L.Order Approves Conforming License Amend Which Will Be Issued & Made Effective When Transfer Completed ML20212G4161999-09-24024 September 1999 Informs of Completion of Licensing Action for Generic Ltr 98-01, Y2K Readiness of Computer Systems at Nuclear Power Plants, for Perry Nuclear Power Plant ML20212A8371999-09-13013 September 1999 Forwards Insp Rept 50-440/99-13 on 990712-30 & Notice of Violation.Insp Included Evaluation of Engineering Support, Design Change & Modification Activities,Internal Assessment Activities & Corrective Actions ML20217A8971999-09-0909 September 1999 Forwards Insp Rept 50-440/99-09 on 990709-0825.One Violation of NRC Requirements Occurred & Being Treated as NCV, Consistent with App C of Enforcement Policy ML20211Q6911999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Perry Operator License Applicants During Wks of 010108 & 15.Validation of Exam Will Occur at Station During Wk of 001218 IR 05000440/19990011999-08-31031 August 1999 Requests That Page Number 4, P2 Status of EP Facilities, Equipment & Resources, of Insp Rept 50-440/99-01 Be Replaced with Encl Rev ML20210Q8421999-08-13013 August 1999 First Final Response to FOIA Request for Documents.Records Listed in App a Being Released in Entirety & Records Listed in App B Being Withheld in Part (Ref FOIA Exempt 5) ML20210R7861999-08-12012 August 1999 Forwards Insp Rept 50-440/99-12 on 990712-16.No Violations Noted.New Emergency Preparedness Program Staff & Mgt Personnel Were Professional & Proactive ML20210K6331999-08-0404 August 1999 Submits Response to Requests for Addl Info to GL 92-01,Rev 1, Reactor Vessel Structural Integrity, for Perry Nuclear Plant,Unit 1 ML20210G8411999-07-28028 July 1999 Informs That Based on Determination That Rev 14 Changes to Various Portions of Perry Nuclear Power Plant Emergency Plan Does Not Decrease Effectiveness of Licensee Emergency Plan & Meets Standard of 10CFR50.47(b),no NRC Approval Required ML20210E0661999-07-22022 July 1999 Forwards Insp Rept 50-440/99-08 on 990518-0708.No Violations Noted.Overall Conduct of Activities at Perry Facility, Conservative & Professional with Continuing Focus on Safety ML20209E5951999-07-0909 July 1999 Ltr Contract:Task Order 46, Perry Engineering & Technical Support (E&Ts) Insp, Under Contract NRC-03-98-021 ML20209D5931999-07-0101 July 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Investigation Rept 3-98-005 Issued on 990510.Corrective Actions Will Be Examined During Future Inspections ML20196H9641999-06-29029 June 1999 Confirms 990615 Telcon Request with J Lieberman for Addl Time to Respond to Enforcement Action 99-012.FirstEnergy Has 60 Days to Respond to EA ML20195G6741999-06-10010 June 1999 Forwards Insp Rept 50-440/99-03 on 990407-0517.Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20207G3921999-06-0808 June 1999 Forwards Notice of Consideration of Approval of Transfer of License DPR-58 & Issuance of Conforming Amend & Opportunity for Hearing Re 990505 Application ML20207B7341999-05-26026 May 1999 Forwards Correction of Typo in TS Table 3.3.6.1-1 for Plant, Unit 1 DD-99-08, Informs That to Extent That Union of Concerned Scientists Requests Commission Undertake Formal Review of DD-99-08 & Hold Meeting to Directly Receive View on Decision,Request Denied.With Certificate of Svc.Served on 9905211999-05-20020 May 1999 Informs That to Extent That Union of Concerned Scientists Requests Commission Undertake Formal Review of DD-99-08 & Hold Meeting to Directly Receive View on Decision,Request Denied.With Certificate of Svc.Served on 990521 ML20207B1251999-05-20020 May 1999 Discusses Investigation Rept 3-98-007 on 981210 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $110,000 IR 05000440/19980181999-05-14014 May 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-440/98-18 on 981110 ML20206Q5181999-05-14014 May 1999 Responds to to SL Hiatt Re Fee Exemption Granted to Firstenergy Nuclear Operating Co,Operator of Perry Nuclear Plant.Action Consistent with Longstanding Policy & Practice,As Well as Legal Requirements ML20196F8081999-05-12012 May 1999 Partially Deleted Ltr Referring to Investigation Case 3-1998-007 Re Determination Whether Recipient Discriminated Against Radiation Protection Supervisor at Perry for Providing Testimony as Witness in DOL Hearing ML20206Q0171999-05-12012 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization, Division of Licensing Project Management Created ML20206S5381999-05-12012 May 1999 Forwards Insp Rept 50-440/99-07 on 990412-16.No Violations Noted.Insp Consisted of Selective Exam of Procedures & Representative Records,Interviews with Personnel & Observation of Activities in Progress ML20206Q2111999-05-10010 May 1999 Discusses Investigation Rept 3-98-005,completed on 990129 & Forwards NOV & OI Rept Synopsis.Circumstances Surrounding Apparent Falsification of Training Records for Individuals Assigned Position in Er Organization Were Investigated ML20196A2961999-05-10010 May 1999 Discusses Investigation Rept 3-98-005 Conducted on 990129 Re Circumstances Surrounding Apparent Falsification of Training Records for Individuals Assigned Positions in Emergency Response Organization & Forwards NOV & Synopsis ML20206H3981999-05-0606 May 1999 Forwards Insp Rept 50-440/99-06 on 990303-04 & 0412-16.No Violations Noted.Inservice Insp Activities Effectively Implemented with Several Aspects Demonstrating Good Safety Focus ML20206N3161999-05-0606 May 1999 Responds to Ltr to NRC on Continued Events Re Transfer of Generation Assets Between Dl & Firstenergy.Info Will Be Considered as NRC Monitor Pending License Transfer Application of Bvps,Units 1 & 2 & Pnpp ML20206H6731999-05-0505 May 1999 Confirms Discussion Between Members of NRC & Recipient Re Meeting Scheduled for 990520 in Lisle,Il to Discuss Operational Issues & Related Topics of Interest to Licensed Operators at Nuclear Power Plants Located in Region III ML20206G6901999-05-0303 May 1999 Forwards Insp Rept 50-440/99-02 on 990225-0406.Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20206G6401999-05-0303 May 1999 Forwards Safety Evaluation Authorizing Relief Requests IR-032 to IR-035 & IR-037 to IR-040 Re Implementation of Subsections IWE & Iwl of ASME Section XI for Containment Insp.Relief Requests IR-36 & IR-41 Withdrawn ML20206D4701999-04-30030 April 1999 Informs That on 990428,FirstEnergy Submitted Post Exam Results of Weld Overlay Repair for Feedwater Nozzle to safe-end Weld at Perry Nuclear Power Plant,Unit 1 (Pnpp) ML20206E2111999-04-29029 April 1999 Discusses Alternative Proposed by Licensee on 990325 & 990401 to ASME BPV Code,Section XI Repair Requirements Along with Separate Alternative to Ultrasonic Exam Acceptance Criteria.Forwards SE Approving Proposed Alternatives ML20205P4041999-04-15015 April 1999 Discusses GL 95-07 Issued by NRC on 950817 & Licensee Responses Submitted on 951016,960213 & 960624 for Perry NPP, Unit 1.Forwards Safety Evaluation Concluding That Licensee Adequately Addressed Actions Requested in GL 95-07 ML20205P0281999-04-12012 April 1999 Provides Individual Exam Results for Applicants Who Took Mar 1999 Initial License Exam.Information Considered Proprietary in Accordance with 10CFR2.790.Without Encls ML20205J5331999-04-0606 April 1999 Ack Receipt of Denying Request from NRC That Addl Info Be Provided Prior to Informal Public Hearing Held on 990222 Re River Bend Station & Perry Nuclear Power Plant 10CFR2.206 Petitions ML20205K5211999-04-0505 April 1999 Forwards Notice of Withdrawal of 970409 LAR on Refueling Interlocks,In Response to Util .Amend Request Will Be Replaced in Future by Similar Request,Based on Approved STS Change Traveler,Number TSTF-225 ML20196K8461999-04-0202 April 1999 Forwards Insp Rept 50-440/99-05 on 990301-05.No Violations Noted.Informs That Licensee Use of 10-Minute Rule & 4-Hour Rule Remains Under NRC Review.Expresses Re Practice Revising Unavailability Criteria on Recurrent Basis ML20205G3891999-03-31031 March 1999 Forwards Safety Evaluation Re Second ten-year Inservice Testing Program Relief Requests.Proposed Alternatives in Relief Requests VR-6,PR-3 & PR-6 May Be Authorized.Relief Request VR-8 Denied ML20205G0441999-03-26026 March 1999 Advises of Planned Insp Effort Resulting from Perry PPR Review,Which Was Completed on 990202.Overall,performance at Perry Was Acceptable ML20205F0011999-03-25025 March 1999 Responds to Re Safety of Perry Nuclear Power Plant & That Plant Operating with Limited Leaks in Three Fuel Rods for Several Months.Informal Public Hearing Re Leaks at Perry Facility Held in Rockville,Md on 990222 ML20205C1611999-03-25025 March 1999 Discusses GL 96-05 Issued on 960918 & Firstenergy 961118, 970317 & 980930 Responses to GL 96-05 Indicating Intent to Implement Provisions of JOG Program on MOV Periodic Verification at Perry Npp.Forwards RAI Re GL 96-05 Program ML20204D8891999-03-17017 March 1999 Forwards Insp Rept 50-440/99-04 on 990222-26.No Violations Noted.Insp Focused on Radiological Planning for Spring 1999 Refueling Outage,On Assessments of Radiation Protection Program & on Radiological Training for General Employees ML20204E7791999-03-17017 March 1999 Forwards Insp Rept 50-440/99-01 on 990113-0224.Non-cited Violation Was Identified ML20207H9921999-03-11011 March 1999 Informs That Requirements to Pay Fee Under 10CFR170 for Review of Pilot Plant Application for Use of Revised Accident Source Term Methodology for Perry Nuclear Power Plant Unit 1,waived for Reasons Stated ML20207K1991999-03-0404 March 1999 Forwards List of Names of Those Individuals & Their Organizational Affiliation as Appropriate,Who Spoke at Informal Public Hearing Re Petitions Filed Pursuant to 10CFR2.206 for River Bend & Perry Plants on 990222 ML20203F8501999-02-11011 February 1999 Forwards Fr Notice to Be Published on 990219 Re Informal 10CFR2.206 Public Hearing Including Video Teleconferencing 1999-09-09
[Table view] |
Text
_ - _ _ _ _
l l -
IAAY 2 01985 l Docket Nos.: 50-440 and 50-441 Mr. Murray R. Edelman, Vice President Nuclear Operations Group The Cleveland Electric Illuminating Company P. O. Box 5000 Cleveland, Ohio 44101 l
Dear Mr. Edelman:
Subject:
NRC Staff Coments on the Offsite Dose Calculation Manual for the Perry Nuclear Power Plant, Unit 1 The staff hcs completed its initial review of the Offsite Dose Calculation Manual (0DCM) submitted by your letter dated February 28, 1985 and its specific comments on the ODCM are enclosed. It is requeste'd that your staff submit a revised ODCM that resolves the staff's comments. Should your staff wish to discuss the enclosed comments, please advise the Perry Project Natiager, John Stefano, accordingly so that appropriate arrangements can be scheduled.
Sincerely, B. J. Youngblood, Chief Licensing Branch No. 1 Division of Licensing
Enclosure:
As stated cc: See next page DISTRIBUTION:
n Docket. File ~ JStefano JSwiff
'NRCPDR ~~' OELD WMeinke LPDR ACRS (16) WGammill NSIC EJordan JHayes PRC System JPartlo.i JFairobent LB#1 R/F BGrimes MRushbrook FCongel
.B#1:DL . M B#1:DL JStefano:kab VL+BJYoungblood 05/20 /85 P05/ 20 /85 8505300338 850520 PDR ADOCK 05000440 i A PDR 1
- o,, UNITED STATES
-e 4. .g NUCLEAR REGULATORY COMMISSION 8, -
' ;j . WASHINGTON, D. C. 20555
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MAY 2 01S85 Docket Nos.: 50-440 J and 50-441 l
1 i
f Mr. Murray R. Edelman,-Vice' President Nuclear Operations Group The Clevelarid Electric Illuminating Company
, P.-0. Box 5000 Cleveland, Ohio 44101
Dear Mr. Edelman:
Subject:
NRC Staff Coments on the Offsite Dosa Calculation Manual i _ for the Perry Nuclear Power Plant,- Unit 1
~
[ The staff has completed its initial review of the Offsite Dose Calculation Manual (0DCM) submitted by your letter dated February 28, 1985 and_its spacific
, . consents 'on the ODCM are enclosed. It is requested that your staff submit a revised ODCM that. resolves the staff's comments. Should your staff wish to discuss the enclosed comments, please advise _the Perry Project Manager, John Stefano, accordingly so that appropriate arrangements can be scheduled.
Sincerely, g/4. w;ba B. J. Youngblood, Chief Licensing Branch No. I Division of Licensing
Enclosure:
As stated cc: See next page c .
PERRY-
[($y p g ,
Mr. Murray R. Edelman, Vice President Muclear Operations Group
_The Cleveland Electric Illuminating Company P. O. Box 5000 Cleveland, Ohio 44101 cc: Jay Silberg, Esq. . Mr. Larry O. Beck Shaw, Pittman, & Trowbridge The Cleveland Electric 1800 M Street, N. W. Illuminating Company Washington, D. C. 20006 P. O. Box 97 E-210 Perry, Ohio 44081 Donald H. Hauser, Esq.
The Cleveland Electric Illuminating Company P. O. Box 5000 Cleveland, Ohio 44101-Resident Inspector's Office U. S. Nuclear Regulatory Commission Parmly at Center Road Perry, Ohio 44081 Regional Administrator y
U. S. NRC, Region III-799 Roosevelt Road Glen Ellyn, Illinois 60137 Donald T.' Ezzone, Esq.
Assistant Prosecuting Attorney 105 Main Street l Lake County Administration Center
[_
Painesville, Ohio 44077 I
Ms. Sue Hiatt OCRE Interim Representative 8275 Munson Mentor, Ohio 44060 Terry J. Lodge, Esq.
618 N. Michigan Street Suite 105 Toledo, Ohio 43624
-John G. Cardinal, Esq.
Prosecutir.g Attorney Ashtabula County Courthouse Jefferson, Ohio 44047-
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ENCLOSURE COMMENTS ON THE PERRY UNIT 1 i 0FFSITE/ DOSE CALCULATION-MANUAL (REV. 0)
Section ~ ,
Comm'ent
- 2.0 Provide in section 2 a flow diagram of the liquid radioactive waste treatment systems, ir.cluding the discharge point and the Radwaste Discharge. Radiation Monitor. This
~
should be a simple diagram with'as little extraneous detail at possible.
2.0/2.2 All potential release points from the PNPP are not batch releases. Some can-be continuous. They include:
(1) Emergency Service Water Loops; (2) Liquid radwaste discharge, sanitary discharge; and (3) Underdrain system ODCM should contain a discussion of these release points.
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2 2.1.2 - From pg 11.2-20 of the FSAR it would appear.that mdf=10,000 rather than 30,000 gpm..
2.1.3L Use of the factor of 1.25 in Equation 2.1-5 is inappropriate. This section does not address how the-Applicant will establish the alarm trip setpoint. -
Suggest reference to other 0DCM's that have been approved. Alarm / trip setpoint should account for effluents such as tritium which are not gamma'or X-ray emitting and would not be seen by gamma scintillation detector..
s Setpoints are usually established based upon the maximum possible flow.
The method presented in Section 2.1.3 would always be based upon the concentration in the release tank and would not be sensitive to changes in release rates.
4 m .a. -
3
-2.2.1 . Equation 2.2-1 should have f as the ,,
maximum possible discharge rate from the given tank.
2.2 Inequations(2.2-2)and(2.2-4),
use of the limiting MPC$ of 10 CFR 20 Appendix B, Table II, Column 2 should be specified.
2.3.1 The ODCM should contain sufficient information to enable calculation of doses for the necessary pathways.
For use in section 2.3.1, additional site specific information should be
. provided. Provide a listing of the points of exposure, the points of withdrawal of drinking water and the points of harvest of aquatic food, identifying the location and the dilution factor Mp for each. Provide i
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. in the ODCM a map showing the locations .
of-the closer-drinking water intakes.
J 2.3.1 -In section 2.3.1, the period of time of exposure bt ,f is set at 15 years.
This should be.the period.to the midpoint'of plant life; if plant life is to be 40 years, then t b
- should be 20 years.
2.3.2 Section 2.3.2 indicates that the Applicant will perform an. analysis of possible impacts through the drinking water pathway with regard '
to the requirements of 40 CFR 141.
Include an explanation of how that analysis will be performed. Provide the necessary site specific data.
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.3.0- . - With section 3.0 Gaseous Effluents, provide flow diagrams of gaseous radioactive Whste treatment systems leading to each of the four environ-mental release points. Show the location of each radioactivity release monitor for gaseous effluents.
Provide the location and a brief description of each release vent point, including whether the vent is equipped with deflector.
3.0/3.1 The steam packing exhauster should be added to this section as a potential release point.
3.1 The determination of the set point seems to imply that each monitor
', - may be allowed to go above.the 500
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6 mrem and 3000 mrem skin limits.
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. Releases should be apportioned to -*
each release point such that the total from all release points is less than 500 mrem whole body and less than 3000 mrem skin.
3.1 Initial estimates of the gaseous source terms for section 3.1.1.
should be provided, especially the
" mix" 1.e., the selection of radio-nuclides and their relative propor-tions.
3.2- In section 3.2, provide a map of the site showing clearly the Site Boundary and the boundary to the Unrestricted Area. Show the compass directions and a scale of distance, such as provided in Figure 5.1-2.
. 3.2.3 In Section 3.2.3, at the bottom of page 37 reference is made to Table n,..__,__.__-__.._... .. .... .. _. _._
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3.2-15 which-is for the average individual. Table 3.2-14, for the maximum indiv'idual, should be referenced here instead.
3.2.3 The abbreviation "ft" for feet should be used throughout, rather than "f". Use of "f" is confusing
- because it is also used for the flowrate; in section 3.2.3 it is used both ways in one definition.
3.2 Pages 51 through 58 appear to be duplicates of pages 14 through 21.
Duplication within the ODCM is not necessary.
4.1 In the third paragraph of Section 4.1, the applicant proposes to seek a variance if it is discovered that' PNPP operations have violated the 40 CFR 190 standard. The intent of the
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- variance provision is to permit continued operation while a problem which might' lead to a violation-is corrected. The variance provision is not a device to expunge a violation which has already occurred..
5.1 In Table 5.1-1, under the Locations column, in addition to the sampling point number, a -brief description should be provided, giving the principal characteristics appropriate for locations for each specific type of sample medium listed. Such infor-mation complements the information
~
provided in Table 5.1-4. ,
5.1 Drinking water sampling (Table 5.1-1)
- should also include the Lake County supply for which the intake is located about 1.5 miles west of PNPP.
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In Table 5.1-4, the sample location descriptions should not rely on "-
markers such as, in Nc. 8, the
- rusted manure spreader which may not be sufficiently permanent.
5.1 Figures 5.1-1 and 5.1-2 are not clear enough. Provide either large, clear foldouts or supplement clear versions of these figures with clear figures giving more detail of the vicinty of sampling locations or groups of locations.
- 5.2 Provide a copy of the_ latest Land Use Census, used to determine the locations for. collecting milk and produce samples and to deternine
_ receptor locations'for dose calcula-tions for various pathways. Include the date the data was gathered.
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APPENDIX A -
PAGES80/81[dentifyTf (a figure or algorithm woul'd suffice) and provide a reference.
PAGE 80 Identify the level of measurement for u (presumably the wind speed at the 10m level).
PAGE 80 Provide the value of-He*
PAGE 80 Provide either a figure indicating the relationship of dl2 to stability and downwind distance or an appropriate reference (e.g. , Regulatory Guide 1.111).
PAGE 80 The description of the information contained in Tables A-2 through A-5 should specify the data base by identifying "the three FSAR years of meteorological data."
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APPENDIX B In the last paragraph of Appendix B, correct the references to tables.
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