ML20247E369
| ML20247E369 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Haddam Neck, 05000000 |
| Issue date: | 09/07/1989 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247E342 | List: |
| References | |
| NUDOCS 8909150268 | |
| Download: ML20247E369 (23) | |
Text
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UNITED STATES
~g .g NUCLEAR REGULATORY COMMISSION
. WASHINGTON, D. C. 20SSS
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CONNECTICUT YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-213 HADDAM NECK PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 122 _.
License No. DPR-61
- 1. The Nuclear Regulatory Commission (the Comission) has found that:
A. The application for amendment by Connecticut Yankee Atomic Power (the licensee), dated May 25, 1989 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
3909150268 890907 PDR ADOCK0500gg3 P
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- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-61 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.122 , are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications. -
- 3. This license amendment is effective as of the date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION ohn F. St z, Director Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 7, 1989 1.
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m___ _ _ . __ . _ _ _
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f - ATTACHMENT TO LICENSE AMENDMENT N0j22 FACILITY OPERATING LICENSE NO. DPR-61
' DOCKET NO. 50-213' p
l Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain. vertical lines indicating the areas of change.
Remove Insert 6-19 6-19 6-22' 6-22 6-23 6-23 2
Y _ _- . _ _- . - -
E.
( .; .
E. - . ADMINISTRATIVE CONTROLS Le. Records o'f reactor tests and experiments.
I f. Records 'of changes made to Operating Proce'dures,
- g. Records of radioactive shipments.
- h. Records of. sealed source leak tests and results.
- i. Records of annual physical inventory of all source material of record.
- j. Radiation and contamination surveys.
6.10.2 The following records' shall be retained for the duration of the -
Facility Operating License:
- a. Record and drawing changes reflecting . facility design modifications made to systems and equipment described in the Facility Description and Safety Analysis Report. '
- b. Records of new and irradiated fuel inventory, fuel transfers, and assembly burnup histories.
- c. Records of facility radiation and contamination surveys.
- d. .Recor'ds of facility radiation and contamination surveys.
- e. Records of gaseous and liquid radioactive material released to the environs.
- f. Records of transient or operational cycles for those facility components designed for a limited number of transients or cycles.
- g. . Records of training and qualification for current members of the plant staff.
- h. Records of in-service inspections performed pursuant to these Technical Specifications.
- i. Records of Quality Assurance activities required by the QA Manual.
J. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
- k. Records of meetings of the PORC and the NRB.
- 1. Records for Environmental Qualification.
- m. Records of reviews performed for changes made to the Radiological Effluent. Monitoring and Offsite Dose Calculation Manual (REM 0DCM) and the Process Control Program.
6-19 Amendment No. 122
H. . '6.17 RADIOLOGICAL EFFLUENT' MONITORING AND OFFSITE DOSE CALCULATION MANUAL
',. (REM 0DCM)
Section I, Radiological Effluent Monitoring Manual (REMM), shall l outline the . sampling and analysis programs to determine the concentration of radioactive materials released offsite as well as L dose commitments to individuals in those exposure pathways and for those radionuclides released as a result of station operation. It shall also specify . operating guidelines for radioactive waste treatment systems and report content.
Section II, the Offsite Dose Calculation Manual (ODCM), shall l describe the methodology and parameters to be used in the calcula-tion of offsite doses due to radioactive gaseous and liquid efflu-ents and in the calculations of gaseous and liquid effluent monitor-ing instrumentation alarm / trip setpoints consistent with the appli-cable LCOs contained in these technical specifications. -
' Changes to the REHODCM:
- a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.m. This ^
documentation shall contain: .
l
- 1) Sufficient information to support the change together with !
the appropriate analyses or evaluations justifying the i change (s) and 2)- A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part-50 and not adversely impact the accuracy or reliabil-ity of effluent, dose, or setpoint calculations.
- b. Shall become effective after review and acceptance by PORC and j the approval of the Station Superintendent.
- c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire REMM or ODCM, as appropriate, as a part of or concurrent with the Semiannual Radioactive Effluent Release Report for the period of the report in which any change was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g.,
month / year) the change was implemented.
6.18 RADIOACTIVE WASTE TREATMENT SYSTEM _S Procedures for liquid and gaseous radioactive effluent discharges from the Unit shall be prepared, P7 roved, maintained and adhered to for all operations involving offsite releases of radioactive efflu-ents. These procedures shall specify the use of appropriate waste treatment systems utilizing the guidance provided in the REM 0DCM.
The solid radioactive waste treatment system shall be operated in accordance with the Process Control Program to process wet radioac-tive wastes to meet shipping and burial ground requirements.
6-22 Amendment No.122
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- 36 19. PASS /Samolina' and Analysis of Plant Effluents l The licensee shall. implement and maintain a program which will ensure the capability to obtain and analyze reactor coolant, radio-active iodines and particulate in plant gaseous effluents, and containment atmosphere samples under accident conditions. This program shall include the following:
2
- a. ' Training of personnel
- b. Procedures for sampling and analysis, and
- c. Provisions for maintenance of sampling and analysis equipment, ,
6-23 Amendment No. 122
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( g ' NUCLEAR REGULATORY COMMISSION i ;r a wAssincTow. o. c. 20sss n' . ,,,, /
NORTl! EAST NUCLEAR ENERGY COMPANY DOCKET NO. 50-245 MILLSTONE' NUCLEAR POWER STATION,. UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 34 ~
License No. DPR-21
- 1. The Nucleer Regulatory Commission (the Commission) has found that:
A. The application for amendment by Northeast Nuclear Energy Company (the-licensee),datedMay 25, 1989 complies with the standards and requirements of the Atomic Energy Act of'1954, as amended (the Act),
.and the Commission's rules and regulations set forth.in 10 CFR Chapter I;
. B. The facility will operate in conformity with the application, the
' provisions of the Act, and the rules and regulations of the
' Comission; C. There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the' health and safety of the public, and-(ii) that such activitier will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common 4
defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
1
4
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-21 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 34 , are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications. --
- 3. This license amendment is effective as of the date of issuance, and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION ohn F. St , rector Project Directorate I-4 Division of Reactor Projects'- I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 7, 1989
JA INISTRATIVE' CONTROLS
/ ,
h '. . Records of sealedisource leak t'ests'and results.
L 'i . Records of ' annual physical inventory of 'all sealed source ,
material of record.
' 6.10. 2. - The'following records shall be retained'for the duration of the
' facility. operating license:
- a. Records and drawing changes reflecting facility design ,
modifications made to systems and equipment' described in the Final Safety Analysis Report.
- b. Records of new and irradiated fuel' inventory, fuel transfers, ~
and assembly burnup' histories.
g
- c. Records of. facility radiation and contamination surveys.
- d. Records of radiation' exposure for' all individuals entering radiation-control areas. .
- e. ' Records of gaseous and liquid radioactive material released .to the environs.
f .- Records of transients or operational cycles for those facility components designed for a limited number of transients or cycles,
- g. Records of training and qualification for current members of
'the plant staff.
- h. . Records of inservice inspections performed pursuant to these Technical Specifications.
i.- Records of quality assurance activities required by the QA Manual.
- j. Records of reviews performed for changes made to procedures or equipment or reviews.of tests and experiments pursuant to 10 CFR Part 50.59.
- k. Records of meetings of the PORC, the NRB, the SORC and the SNRB.
- 1. Records for environmental qualification,
- m. Records of reviews performed for changes made to the Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REMODCM) and the Process Control Program.
'6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
1 Millstone Unit-1 6-20 Amendment No. 34
,6 .
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2 .-
ADMINISTRATIVE CONTROLS
~ 21 Lint'egrated leak test requirements for each system at a frequency not L to exceed refueling cycle intervals.
.6.14 IODINE MONITORING The licensee shall implement a program which will ensure the capability to accurately determine the airborne iodine concentration -in' vital areas under
- " accident conditions This program shall include the following:
1.- Training of personnel,
- 2. Procedures for monitoring, and
- 3. Provisions for maintenance of sampling and analysis equipment.
6.15 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REMODCM)
Section I, Radiological Effluent Monitoring Manual (REMM), shall outline the l sampling and analysis programs to determine the concentration of radioactive materials released offsite. as well as dose commitments to individuals in those exposure pathways and for those radionuclides released as a result of station
, operation. It shall also specify operating guidelines for radioactive waste treatment ~ systems and report content.
Section II, the 10ffsite ' Dose Calculation Manual (ODCM), shall describe the l' methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and . liquid effluents and in the calculation of gaseous and liquid effluent rponitcring instrumentation alarm / trip setpoints consistent with the applicable LCOs contained in these technical specifications.
Changes to the REMODCM:
- a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.m. This documentation shall contain:
- 1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s),
and
- 2) A determination that the change will maintain the level of !
radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190,10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adverseiy impact the accuracy or reliability of effluent, dose, or setpoint calculations.
- b. Shall become effective after review and acceptance by SORC and the approval of the Station Superintendent. ,
Millstone Unit 1 6-22 Amendment No. 34
- _ _ _ _ _ . __ _ i
, c. Shall be submitted to the Commission in the form of a complete,
.. legible copy of the entire REMM or ODCM, as appropriate, as a part of or concurrent with the Semiannual Radioactive Effluent Release-Report for the period of the report in which any change was -made. 1 Each change shall be identified by markings in the margin of the I affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented, j l
6.16 RADI0 ACTIVE WASTE TREATMENT Procedures for liquid and gaseous radioactive effluent discharges from the Unit shall be prepared, approved, maintained, and adhered to for all 3 operations involving offsite releases of radioactive effluents. These procedures shall specify the use of approprate* waste treatment utilizing '
the guidance provided in the REM 0DCM.
- The solid radioactive waste treatment system shall be operated in accordance with the process Control Program to process wet radioactive wastes to meet shipping and burial ground requirements.
i Millstone Unit 1 6-23 Amendment No. 34
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'o,, UNITED STATES NUCLEAR REGULATORY COMMISSION t WASHINGTON, D. C. 20'i55
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t NORTHEAST E NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 .
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.143 License No. DPR-65
- 1. The Nuclear Regulatory Commission (the Comission) has found that:
A. The-application for amendment by Northeast Nuclear Energy Company, et s.l. (the licensee), dated May 25, 1989 complies with the standards and requirements of the Atomic Energy Act of-1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; '
B. The facility will operate in conformity with the application, the ,
provisions of the Act, and the rules and regulations of the i Commission; C. There .is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activit.ies will be conducted in compliance with the Comission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
l l
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1
- 2. .Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, ;
and paragraph 2.C.(2) of Facility Operating License No. DPR-65 is hereby amended to read as follows:
(2)- Technical Specifications ,
The Technical Specifications contained in Appendix A, as revised l through Amendment No.143, are hereby incorporated in the license. '
The licensee shall operate the facility in accordance with the ;
Technicr1 Specifications. - - -
- 3. .This license amendment is effective as of the date of issuance, and shall be implemented within 30 days of issuance.
FOR THE NUCLEA REGULATORY COMMISSION John F. St z, Director M roject Directorate I-4
/ Division of Reactor Projects - I/II ;
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 7,1989 l
l m_______ .___--
1 J .;
ATTACHMENT TO LICENSE AMENDMENT NO.143 n.
L FACILITY OPERATING LICENSE NO. DPR-65 DOCKET NO. 50-336 1
1 )
. Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change. The corresponding overleaf pages are provided to maintain document completeness.
Remove Insert
~
6-21 6-21 6-23 6-23 6-24 6-24
-_m__-____
, ADMINISTRATIVE CONTROLS
- g. Records of training and qualification for current members of the plant
. staff.
- h. Records of inservice inspections performed pursuant to these Technical Specifications.
- i. Records of quality assurance activities required by the QA Manual.
- j. Records of reviews performed for changes made to procedures or equipment. or reviews of tests and experiments pursuant to 10 CFR Part 50.59.
- k. Records of meetings of the PORC, the NRC, the SORC and the SNRB.
- 1. Records of Environmental Qualification which are covered under the _..
provisions of paragraph 6.13.
- m. Records of reviews performed for changes made to the Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REM 0DCM) and the Process Control Program.
6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure. .
6.12 HIGH RADIATION AE A 6.12.1 In lieu of the " control device" or "al arm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall' be barricated and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit *. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
- a. A radiation monitoring device which continuously indicates the radiation dose rate in the area.
- b. A radiation monitoring device which continuously integrates the ,
radiation dose rate in the area and alarms when a preset '
integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel have been made knowledgeable of them.
- Health Physics personnel or personnel escorted by Health Physics personnel
! shall be exempt from the RWP issuance requirement during the performance of l their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.
MILLSTONE - UNIT 2 6-21 Amendment No. 143
t s
- ADMINISTRATIVE CONTROLS 6.15 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REM 0DCM)
Section I, Radiological Effluent Monitoring Manual (REMM), shall outline the l sampling and analysis programs to determine the concentration of radioactive i materials released offsite as well as dose commitments to individuals in those exposure pathways and for those radionuclides released as a result of station !
operation. It shall also specify operating guidelines for radioactive waste treatment systems and report content.
Section II, the Offsite Dose Calculation Manual (ODCH), shall describe the l methodology and parameters to be used in the calculation of offsite doses due -
to radioactive gaseous and liquid effluents and in the calculation of gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints consistent with the applicable LCOs contained in these technical specifications.
Changes to the REM 0DCM:
- a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.m. This documentation shall contain:
l
- 1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s), !
and
- 2) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR ,
Part 190,10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and '
not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations. l
- b. Shall become effective after review and acceptance by SORC and the approval of the Station Superintendent.
- c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire REMM or ODCM, as appropriate, as a part of or concurrent with the Semiannual Radioactive Effluent Release Report for the period of the report in which any change was made. ,
Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was
! changed, and shall indicate the date (e.g., month / year) the change was implemented. ,
6.16 RADI0 ACTIVE WASTE TREATF "I l Procedures for liquid and gaseous radioactive effluent discharges from the Unit shall be prepared, approved, maintained, and adhered to for all operations involving offsite releases of radioactive effluents. These procedures shall specify the use of approprate* waste treatment utilizing the guidance provided in the REM 0DCM.
MILLSTONE - UNIT 2 6-23 Amendment No. 143
v LThe Solid Radioactive Waste Treatment system shall be operated in accordance1with the Process Control Program to process wet radioactive wastes to meet shipping and burial ground requirements.
6.17~ SECONDARY WATER CHEMISTRY A program shall be maintained for monitoring of secondary water chemistry to j inhibit steam generator tube degradation. - This program shall include: j
- 1. Identification of a sampling schedule for the critical variables and i
. control points for these variables, j 2- Identification of the procedures used to measure the values of the l critical variables,
- 3. Identification of process sampling points, which shall include monitoring the discharge of the condensate pumps for evidence of condenser in-leakage,
- 4. Procedures _for the recording and management of data,
- 5. Procedures defining corrective actions for all off-control point chemistry conditions, and
- 6. A procedure identifying: (a) the authority responsible for the 1 interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action.
6.18 PASS /Samolina and Analysis of Plant Effluents A program shall be established, implemented and maintained which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulate in plant gaseous effluents, and containment atmosphere samples under accident conditions. The program shall include the following:
(i) Training of personnel, (ii) Procedures for sampling and analysis, ;
(iii) Provisions for maintenance of sampling & analysis
(
r MILLSTONE - UNIT 2 6-24 Amendment No. 143
- / 'o UNITED STATES j ." g[ NUCLEAR REGULATORY COMMISSION l
t : E WASHINGTON, D. C. 20555 '
- g,
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NORTHEAST NUCLEAR ENERGY COMPANY, ET AL.
DOCKET NO. 50-423 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 3 i AMENDMENT TO FACILITY OPERATING LICENSE I
~'
Amendment No. ,40 License No. NPF-49
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Northeast Nuclear Energy Company, etal.(thelicensee)datedMay 25, 1989 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the pmvisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and !
safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
i I
)
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i'
-,,6
-J
-2
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, ;
and paragraph 2.C.(2) of Facility Operating License No. NPF-49 is hereby {
amended to read as follows:
(
-(2) Technical Specifications "
i The Technical Specifications contained in Appendix A, as revised i through Amendment No.40 , and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license. The licensee shall operate the "
facility in accordance with the Technical Specifications and the Environmental Protection Plan. -
- 3. This license amendment is effective as of the date of its issuance, and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION ohn F. St , irector Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 7, 1989 l'
L
..J.* :y' r.. .
, ' ATTACHMENT.TO LICENSE: AMENDMENT NO. 40- i l
FACILTIY OPERATING LICENSE NO. NPF -DOCKET NO. 50-423 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. - The revised pages are identified by amendment number and l
!- -contain vertical lines indicating the areas of change. The corresponding overleaf pages are' provided to maintain document completeness.
i Remove Insert' i 6-23 6-23
'6-25 6-25 I
l i
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l t _ --
o .
q s
I .
ADMINISTRATIVE CONTROLS 1
RECORD RETENTION (Continued)'
d.. Records of gaseous and liquid radioactive material released to the environs;
- e. Records of transient or operational cycles for those unit components-identified in Table 5.7-1;
- f. Records of reactor tests and experiments; I
- g. Records of- training and qualification for current members of the !
unit staff;
- h. Records of inservice inspections performed pursuant to these Technical Specifications;
- i. Records of quality assurance activities required by the Quality j Assurance Topical Report not listed in Specification 6.10.2;
- j. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59;
- k. Records of meetings of the PORC, the NRB, the SORC, and the SNRB;
- 1. Records of ' t.he service lives of all hydraulic and mechanical snubbers required by Specification 3.7.10 including the date at which the service life commences and associated. installation' and maintenance records;
- m. Records of secondary water sampling and water quality; and
- n. Records of analyses required by the Radiological Environmental Monitoring Program that would permit evaluation of the accuracy of the analysis at a later date. This should include procedures effective at specified times and QA records showing that these procedures were followed.
- o. Records of reviews performed for changes made to the Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REM 0DCM) and the Process Control Program. '
6.11 RADIATION PROTECTION PROGRAM 6.11.1 Procedures for personnel radiation protection shall be prepared consistent I with the requirements of 10 CFR Part 20 and shall be approved, maintained, and adhered to for all operations involving personnel radiation exposure.
6.12 HIGH RADIATION AREA 6.12.1 Pursuant to paragraph 20.203(c)(5) of 10 CFR Part 20, in lieu of the
" control device" or " alarm signal" required by paragraph 20.203(c),each high radiation area, as defined in 10 CFR Part 20, in which the intensity of radia-tion is equal to or less than 1000 mR/h at 45 cm (18 in.) from the radiation source or from any surface which the radiation penetrates shall be barricaded MILLSTONE - UNIT 3 6-23 Amendment No. 40
i
- l " ADMINISTRATIVE CONTROLS
.6.13 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REM 0DCM) 1 Section I, Radiological Effluent Monitoring Manual (REMM), shall outline the j sampling and analysis programs to determine the concentration of radioactive
. materials released offsite as well as dose commitments to individuals in those i exposure pathways and for those radionuclides released as a result of station operation. It shall also specify operating guidelines for radioactive waste treatment systems and report content. i Section II, the Offsite Dose Calculation Manual (ODCM), shall describe the l methodology and parameters to be used in the calculation of offsite doses due i to radioactive gaseous and liquid effluents and in the calculations of gaseous -- l and liquid effluent monitoring instrumentation alarm / trip 'setpoints consistent with the applicable LCOs contained in these technical specifications, j Changes to the REM 0DCM:
- a. Shall be documented and records of reviews performed shall be retained as ,
required by Specification 6.10.30. This documentation shall contain: *
- 1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s), and
- 2) A determination that the change will maintain the level of radioac- :
tive effluent control required by 10 CFR 20106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
- b. Shall become effective after review and acceptance by SORC and the approval of the Station Superintendent.
- c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire REMM or ODCM, as appropriate, as a part of or concur-rent with the Semiannual Radioactive Effluent Release Report for the period of the report in which any change was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the i date (e.g., month / year) the change was implemented.
6.14 RADIOACTIVE WASTE TREATMENT Procedures for liquid and gaseous radioactive effluent discharges from the Unit shall be prepared, approved, maintained and adhered to for all operations I involving offsite releases of radioactive effluents. These procedures shall specify the use of appropriate waste treatment systems utilizing the guidance provided in the REM 00CM.
The Solid Radioactive Waste Treatment System shall be operated in accordance with the Process Control Program to process wet radioactive wastes to meet shipping and burial ground requirements.
MILLSTONE - UNIT 3 6-25 Amendment No. 40 l