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Category:Inspection Report Correspondence
MONTHYEARML21125A1402021-05-0404 May 2021 OPC Document Request -Feb 2021 IR 05000220/20184102018-10-16016 October 2018 Material Control and Accounting Program Inspection Report 05000220/2018410 and 05000410/2018410 (Letter Only) JAFP-15-0146, Response to Ti 2515/190: Inspection of the Proposed Interim Actions Associated with Near-Term Task Force Recommendation 2.1 Flooding Hazard2015-12-0909 December 2015 Response to Ti 2515/190: Inspection of the Proposed Interim Actions Associated with Near-Term Task Force Recommendation 2.1 Flooding Hazard IR 05000333/20070012007-03-0202 March 2007 Annual Assessment Letter - James A. Fitzpatrick Nuclear Power Plant (Report 05000333-07-001) IR 05000220/20070012007-03-0202 March 2007 Annual Assessment Letter - Nine Mile Point Nuclear Station (Report 05000220-07-001 and 05000410-07-001) IR 05000333/20060092006-10-17017 October 2006 IR 05000333-06-009, James A. FitzPatrick Nuclear Generating Station; Ti 2515/168 ML0527205072005-09-29029 September 2005 Requalification Program Inspection - Nine Mile Point Nuclear Station, Unit 2 ML0534600942005-09-12012 September 2005 Inspection Request, NMP PI&R - IR 2005-007 IR 05000333/20040052005-02-0202 February 2005 IR 05000333-04-005, on 10/01/2004 -12/31/2004, James A. FitzPatrick Nuclear Power Plant; Post Maintenance Testing, Problem Identification and Resolution, Event Follow-up IR 05000220/20040052005-01-26026 January 2005 IR 05000220-04-005, 05000410-04-005; on 10/01/2004 - 12/31/2004; Nine Mile Point, Units 1 and 2; Licensed Operator Requalification Program and Operability Evaluations IR 05000220/20030082003-06-16016 June 2003 IR 05000220-03-008, IR 05000410-03-008, on 05/05/2003 - 05/08/2003, Nine Mile Point Nuclear Station Unit 1 and Unit 2, Temporary Instruction 2515/148, Inspection of Nuclear Reactor Safeguards Interim Compensatory Measures. ML0308500772003-03-26026 March 2003 Notification of Conduct of a Triennial Fire Protection Baseline Inspection IR 05000220/20020042002-07-19019 July 2002 IR 05000220-02-004, IR 05000410-02-004, on 05/19-06/29/2002, Nine Mile Point Nuclear Station, LLC, Nine Mile Point, Units 1 & 2. Resident Inspector Report IR 05000220/20020032002-06-0707 June 2002 IR 05000220-02-03, IR 05000410-02-03, on 3/31-5/18/2002; Nine Mile Point Nuclear Station, LLC; Nine Mile Point, Units 1 & 2. Resident Inspector Report. No Violations Identified IR 05000220/20020022002-04-26026 April 2002 IR 05000220/2002-002, IR 05000410/2002-002, on 2/17-4/6/2002; Nine Mile Point Nuclear Station, LLC; Nine Mile Point, Units 1 & 2. Resident Inspector Report. No Violations Identified IR 05000333/20010132002-03-25025 March 2002 IR 05000333/2001-013, on 01/01 - 02/09/02; Entergy Nuclear Northeast, James A. FitzPatrick Nuclear Power Plant, Temporary Plant Modifications. Non-cited Violations Noted IR 05000220/20010112002-03-21021 March 2002 IR 05000220/2001-011, IR 05000410/2001-011, on 12/30/01-02/15/2002; Nine Mile Point Nuclear Station, LLC; Nine Mile Point, Units 1 & 2. Emergency Work Control. Non-cited Violations Identified IR 05000220/20010102002-01-24024 January 2002 IR 05000220/2001-010, IR 05000410/2001-010, on 11/11-12/29/2001; Nine Mile Point Nuclear Station, LLC; Nine Mile Point, Units 1 & 2. Resident Inspector Report. No Violations ML18018B0742000-03-27027 March 2000 ADAMS Distribution Notification ML17037C1621974-09-0404 September 1974 Letter Referring to Two Significant Matters Identified During the August 26 to 30, 1974 Inspection at Nine Mile Point-1 Reactor Facility ML17037C2091974-06-13013 June 1974 Letter Responding to the May 30, 1974 Letter Informing the Commission of the Corrective and Preventive Actions in Response to a May 15, 1974 Letter ML17037C2141973-11-14014 November 1973 Letter Responding to the September 13, 1973 Informing the Commission of the Action Taken to Correct the Items of Noncompliance Following the Recent Inspection and Advising That the Action Will Be Verified During the Next .. ML17037C2151973-10-25025 October 1973 Letter Responding to the September 10, 1973 Letter Informing the Commission of the Action Taken to Correct the Item of Noncompliance Brought to Attention Following the Recent Inspection and Advising That Corrective Action .. ML17037C1111972-08-10010 August 1972 Letter Regarding Action Taken in Response to a June 22, 1972 Letter Relating to Wall Thickness of Nuclear Service Valves ML17037C0991972-05-10010 May 1972 Letter Responding to an April 14, 1972 Letter Requesting Results of the Inspection on the Pressure Suppression Torus 2021-05-04
[Table view] Category:Letter
MONTHYEARIR 05000333/20230042024-02-0707 February 2024 Integrated Inspection Report 05000333/2023004 and Independent Spent Fuel Storage Installation Inspection Report 07200012/2023001 ML24037A0102024-02-0606 February 2024 Requalification Program Inspection NMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024 Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24018A0012024-01-18018 January 2024 Notification of Commercial Grade Dedication Inspection (05000333/2024010) and Request for Information ML24004A2302024-01-0808 January 2024 Project Manager Reassignment ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations ML23354A0012024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23356A0832024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0058 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) JAFP-23-0065, License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications2023-12-14014 December 2023 License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023 Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 IR 05000333/20234012023-12-0808 December 2023 Cybersecurity Inspection Report 05000333/2023401 (Cover Letter Only) JAFP-23-0069, Supplemental Response to Part 73 Exemption Request Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements RS-23-126, Request for Exemption from 10 CFR 2.109(b)2023-12-0707 December 2023 Request for Exemption from 10 CFR 2.109(b) ML23291A4642023-12-0707 December 2023 Issuance of Amendment No. 251 Regarding the Adoption of Title 10 the Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of SSC for Nuclear Power Plants NMP1L3564, Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements ML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b NMP1L3563, Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-12-0404 December 2023 Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) IR 05000220/20234022023-11-28028 November 2023 Security Baseline Inspection Report 05000220/2023402 and 05000410/2023402 NMP1L3557, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation JAFP-23-0057, and Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 and Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation JAFP-23-0064, Emergency Plan Document Revision2023-11-15015 November 2023 Emergency Plan Document Revision JAFP-23-0063, Registration of Spent Fuel Cask Use2023-11-13013 November 2023 Registration of Spent Fuel Cask Use IR 05000333/20230032023-11-13013 November 2023 Integrated Inspection Report 05000333/2023003 ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000220/20234202023-11-0101 November 2023 Security Baseline Inspection Report 05000220/2023420 and 05000410/2023420 ML23305A0052023-11-0101 November 2023 Operator Licensing Examination Approval IR 05000333/20230102023-10-26026 October 2023 Biennial Problem Identification and Resolution Inspection Report 05000333/2023010 IR 05000220/20230032023-10-25025 October 2023 Integrated Inspection Report 05000220/2023003 and 05000410/2023003 JAFP-23-0059, Registration of Spent Fuel Cask Use2023-10-24024 October 2023 Registration of Spent Fuel Cask Use IR 05000333/20233012023-10-19019 October 2023 Initial Operator Licensing Examination Report 05000333/2023301 IR 05000220/20235012023-10-17017 October 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000220/2023501 and 05000410/2023501 IR 05000220/20230112023-10-16016 October 2023 Comprehensive Engineering Team Inspection Report 05000220/2023011 and 05000410/2023011 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans NMP1L3554, Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases2023-10-0606 October 2023 Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases C IR 05000220/20233032023-09-20020 September 2023 Retake Operator Licensing Examination Report 05000220/2023303 ML23250A0822023-09-19019 September 2023 Regulatory Audit Summary Regarding LARs to Adopt TSTF-505, Rev. 2, and 10 CFR 50.69 ML23257A1732023-09-14014 September 2023 Requalification Program Inspection IR 05000220/20230052023-08-31031 August 2023 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2023005 and 05000410/2023005) IR 05000333/20230052023-08-31031 August 2023 Updated Inspection Plan for James A. FitzPatrick Nuclear Power Plant (Report 05000333/2023005) JAFP-23-0048, Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2023-08-31031 August 2023 Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-23-0050, Physical Security Plan, Revision 242023-08-31031 August 2023 Physical Security Plan, Revision 24 JAFP-23-0047, Correction to the 2022 Annual Radioactive Effluent Release Report2023-08-30030 August 2023 Correction to the 2022 Annual Radioactive Effluent Release Report RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs NMP2L2851, Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations2023-08-25025 August 2023 Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations 2024-02-07
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X' '.-l UNITED STATES AT~Iv\IC ENERGY COMMISSION p.'< '~ff*Tr. Or ff CGVLATOffY Ofhf-:ftATI Rl'CION l 8@8 ~PM 631 PARK AVENUE
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>IflII OI JUN 131974 Niagara Mohawk Power Corporation License Nos. DPR-17/CPPR-70 Attention: Hr. R. R. Schneider Inspection Nos. 50-220/74-06 Vice President, Operations 50-333/74-17 300 Erie Boulevard, Hest Syracuse, New York 13202
Reference:
Your letter dated May 30, 1974
-Inmes'pons'o our"letter dated Hay 15, 1974 Gentlemen:
Th;Ink you for informing us of the corrective and preventive actions you. documented in response to our correspondence. These actions will be examined during our next inspection of your licensed program.
Your cooperation with us is appreciated.
Sincerely, Paul R. Nelson, Chief Radiological and Environmental Protection Branch cc: T. J. Perkins, Station Superintendent Mr. A.Z. Roisman, Counsel for C'itizens Committee for Protection of the Environment Berlin, Roisman and Kessler 1712 N Street, Northwest Ilashington, D.C. 20036
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NIAGARA MOHAWK POWER CORPORATION NIAGARA Q MOHAWK 300 EBIE OOVLEVABD %VEST SYBACUSE. N. Y. 13202 May 30, 1974 hir. Paul R. Nelson, Chief Radological and Environmental Protection Branch United States Atomic Energy Commission Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406
Dear Mr. Nelson:
Following a thorough review of your hfay 1S, 1974 letter, regarding the inspection conducted by Mr. Bores of. your office on April 22-26, 1974 at Nine Mile Point Nuclear Station llnit 1 and .Iames A. FitzPatrick Nuclear Power Plant, we conclude that there is no information in the report to be withheld from public disclosure.
Concerning the alleged violations of AEC requirements as numerated in your report the following information pursuant to provision of Section 2.201 of the AEC's "Rules of Practice", Part 2, Title 10, Code of Federal Regulations is submitted:
Section 4.6.1 and Table 4.6.18 of the Technical Specifications require that air particulates be sampled on a weekly basis at five on-site and six oFf-site stations.
Contrary to this requirement, air particulates >>ere not sampled at one of these stations, Dl On-Site, for 31 of 47 sampling periods from November 9, 1972 through September 29, 1973.
RESPONDS It should be pointed out that during. this period sampling was
.required for only 23 of the 47 periods because of the Fact that >>e >>ere in Grade A of the environmental program (i.e.,
stack release rate <1/30Q).
0 ~ g her. Paul R. Nelson, hiay 30, 1974 Atomic, Energy Commission }
h An investigation oF the operation of Dl on-site air sampler shows the Following:
History on Station Dl On-Site:
No oF Samples Required No of Sample Dates Land Pro ram Grade Prom Di On-Site Collected 4/1/72 w 11/1/72 None 27 1.1/1/72 -}. 3/1/73 17 3/1/73 ~ 4/15/73 ~ 3 4/15/73 ~ll/1/73 None 12 11/1/73 ~ 4/1/74 20 20 Total samples required from Sample Station Total samples collected as required 31 Required samples missing 13 Along with this sampler we also operated 10 other samplers as part of the survey program. During the year 1973 a total of 544 environmental air samples were collected while 28 were reported as missing samples. This is an overall recovery rate of approximately 95'~.
The required samples were not collected because of mal-functions of the sampling equipment. These included:
- l. Burned out motor in sample pump.
- 2. 1:aulty fan on housing cooling system resulting in overheated motor and blown fuses.
- 3. Pump motor - faulty switch.
- 4. Pump piston freeze up.
- 5. Faulty thermostat on housing resulting in improper fan operation and subsequent over-heating of pump motor.
The major problem was discovered to be a faulty thermostat (see item 5. above); once this was replaced, November 14, 1973, the sampler operated satisfactorily.
h)r. )'aul R. Nelson, hfa~x0, 1974 Atomic Energy Commissio>~
The new Environmental Technical Specification which will go into efFect when the commission issues the NhiP-1 per-manent operating license >>ill allow an air sample station to be taken out of service on occasion (i.e., at least 10 out of 1S samplers shall be. operateil) .. This snccification
'recognizes the Fact that these sample stations are not continuousl> attended <<nd that if a pum)i trips>>hi le a technician is not in attendance a whole >>eek's sample is lost'n the future >>e will make every effort to maintain the environmental sampling equipment so t)iat required samples are collected. h'ith the increased work load due to the new ETS requirements we have recently added to the site staff >>'ho >>ill be responsible For the implementation of the environmental survey program.
- 2. Section 4.6.1 and Table 4.6.18 of the ')'echnical Specifications require that air particulate samples be analyzed monthly from five on-site and six off-site stations.
Contrary to this requi~'ement, the weekly air particulate filters were composited prior to analysis. In some instances, the five on-site samples were composit'ed into one sample and the six off-site samples were composited as a second sample prior to analysis. At other times all of the filters were composited into a single sample prior. to gamma spectral analysis.
RESPONDS A beta count was performed on each environmental air particulate sample on a low background beta counter. This is the most mean-ingful way to count these samples. Gamma spectral analysis using our present equipment is not sensitive enough to measure the low level of activity encountered in environmental samples.
The particulate air samples >>ere composited .to be counted on a 3 x 3 NaI gamma ray analyzer crystal because of the'low activity of the individual samples, the high background inherent in an in-plant Nal system and the low sensitivity of an in-plant NaI system.
If a significant difference bet>>een on-site and oFF-site gross beta analysis appears gamma analysis on a sensitive system is one wa> of isolating and examining these differences. To be
e h/r. Paul R. Nelson, l1a~30, 1974 Atomic Energy Commissio~
The ne>> Environmental Technical Speci Fication which will go into effect when the commission issues the Ni~lp-1 per-manent operating license will allow an air samnle station to be taken out of service on occasion '(i.e., at least 10 out of 15 samplers shall be operated) . This speciFication
'recognizes the Fact that these sample stations are not continuousl> attended and that iF a pump trips >>hile a technician is not in attendance a whole >>eck's sample is lost.
In the future we >>ill make every eFFort to maintain the environmental sampling equipment so that required samples are collected. b'ith the increased >>ork load due to the new ETS requirements we have recently added to the site staff >>'ho will be responsible for the implementation of the environmental survey program.
- 2. Section 4.6.1 and Table 4.6.1B of the Technical Specifications require that air particulate samples be analyzed monthly from five on-site and six off-site stations.
Contrary to this requirement, the weekl>'ir particulate filters >>ere composited prior to analysis. In some inst inces, the five on-site samples >>ere composited into one sample and the six off-site samples >>ere composited as a second sample prior to analysis. At other times all of, the filters were composited into a single sample prior to gamma spectral analysis.
RESPONDS A beta count was performed on each environmental air particulate sample on a low background beta counter. This is the most mean-ingful way to count these samples. Gamma spectral analysis using our present equipment is not sensitive enough to measure the low level of activity encountered in environmental samples.
The particulate air samples were composited to be counted on a 3 x 3 NaI gamma ray analyzer crystal because of the low activity of the individual samples, the high background inherent in an in-plant NaI system and the lo>> sensitivity of an in-plant NaI system.
If a significant difference between on-site and off-site gross beta analysis appears gamma analysis on a sensitive system is one wa> of isolating and examining these diFFerences. To be
" 'fr. Paul R. Nelson, Ma0, 1974 Atomic Energy Commission meaningful, however, the samples would have to be sent to a contractor for special analysis. On-site and off-sitc samples at Nine llile Point do not sho<< any significant differences. A review of thc gross beta data of air part-iculates for the second half of 1973 shows that the on-site samples averaged .042 pci/m while the off-site samples averaged 0.045 pci/m~. Even during periods oF high off-gas activity (i.e., >>hen release rates are greater than 1/10Q) the on-site and off-site samples do not sho>>
significant diFferences.
The new Environmental Tcchnical Specifications will allo>>"
compositing of the on-site samples and the off-site samples.
Until these specifications tako effect we will perform a gamma spectral analysis on each air particulate sample individually. Ne will also perform some of the analysis at the James A. FitzPatrick laboratory in an attempt to see if gxeater sensitivity can be obtained using the Geli counting system there.
Section 4.6.1 and Table 4 .6.1A of the Technical Specifications require that fish, clams and gammarus be- sampled at two locations each Spring and Fall and analyzed for gross beta activity.
Contrary to this requirement, gxoss beta analyzes <<'ere not performed on thc above media since 1971.
RESPONDS 4'hen our environmental lake program was fixst instituted because of the complexity of the analysis we were required to send all of our aquatic biota samples to a contractor for analysis. li'e requested that he run gross beta analysis, gamma scans and specific radiochemical analysis on Co Zn65, Sr and Cs' After a fe>> years oF analyzing the samples in this manner we realized that gross beta analysis was n'ot meaningful (it only accounted for natural K'ctivity),
that gamma scans >>ere not meaningful (all samples were reported as "not detectable" ) and oF the 4 isotopes which were being radiochemical 1> analyzed only Co6 was significant.
In 1972 we felt that the state of the <
~ lv 0 0 her. Paul R. Nelson, May 30, 1974 Atomic Energy Commission The ne>>'nvironmental Technical SpeciFications list GeLi analysis and Sr ~, Sr as the method of analysis For aquatic biota. Until these ne>> specifications go into
.effect >>e >>ill request that in addition our contractor perform a gross beta analysis on all biota samples.
h Very truly yours, Original Signed by R.R. Schneider R.R. Schneidel Vice President - Electric Onerations RRS/bar