ML20046A587
| ML20046A587 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 07/19/1993 |
| From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML20046A585 | List: |
| References | |
| NUDOCS 9307290074 | |
| Download: ML20046A587 (12) | |
Text
{{#Wiki_filter:, t ATTACHMENT 1 CONSUMERS POWER COMPANY BIG ROCK POINT PLANT DOCKET 50-155 TECH SPEC CHANGE REQUEST AS PROPOSED PAGES I i i r I ? 9307290074 930719 17 PDR ADOCK 050001S5 S P PDR Q3 BP0ATH.JLL i )
ADMINISTRATIVE CONTROLS 6.9.2.1 (Contd) The annual radiological environmental operating reports 'shall-include summarized and tabulated results of all radiological environmental samples taken during the report p.eriod. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be - submitted as soon as possible in a supplementary report. The reports shall also include the following: a summary description of the radiological environmental monitoring program including sampling methods for each sample type, a map of all sampling locations keyed to a table giving distances and directions from the reactor and the results of land use census required by the Specification 13.2.3., and results of the interlaboratory comparison program required by Specification 13.2.4. 6.9.2.2 Annual Radioactive Effluent Release Report / A. Radioactive Effluent Release A report shall be submitted to NRC as required per 10 CFR / 50.36a(a)(2). / 1. Gaseous Effluents a. Gross Radioactivity Releases (1) Total gress radioactivity (in curies), including noble and activation gases released. (2) Maximum gross radioactivity release rate during any one-hour period. (3) Total gross radioactivity (in curies) by nuclide released, based on representative isotopic arialyses performed. (4) Percent of Technical Specifications limit. b. lodine Releases (1) Total iodine radioactivity (in curies) by nuclide released, based on representative isotopic analyses performed. 84 AS PROPOSED
l ADMINISTRATIVE CONTROLS 6.12.1 (Contd) c. A radiation protection qualified individual (e.g.,- Health Physics Technician) with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within l the area, and shall perform periodic radiation surveillance as specified by the Chemistry and Radiation Protection Supervisor in the RWP. 6.12.2 In addition to the requirements of Specification 6.12.1, areas accessible to personnel with radiation levels greater than 1000 mR/h at 45 cm (18 in.) from the radiation source or from any surface from which the radiation penetrates shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or health physics supervision. Doors shall remain locked except i during periods of access by personnel under an approved RWP which shall l specify the dose rate levels in the immediate work areas and the maximum allowable stay time for individuals in that area. In lieu of the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by i personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area. For individual high radiation areas accessible to personnel with radiation levels of greater than 1000 mR/h that are located within large areas where no enclosure exists for purposes of locking, and no enclosure can be l reasonably constructed around the individual areas, then that individual area shall be barricaded, conspicuously posted, and a flashing light shall be activated as a warning device. 6.13 ENVIRONMENTAL OVALIFICATION l J (Deleted) ~ 6.14 PROCESS CONTROL PROGRAM (PCP) 6.14.1 Changes to the PCP shall be submitted to the Commission in the l Radioactive Effluent Release Report for the period in which / the change (s) was made effective. This submittal shall contain: 1 a. Sufficiently detailed information to support the rationale for j the change b. A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and i c. Documentation of the fact that the change has been reviewed and approved by the responsible Nuclear Operations Department per CPC-2A (Quality Program). j 90 AS PROPOSED ]
} ADMINISTRATIVE CONTROLS i 6.15' 0FFSITE DOSE CALCULATION MANUAL (ODCM) 6.15.1 Changes to the ODCM shall be submitted to'the Commission in the j Radioactive Effluent Release Report for' the period in which /- the change (s) was made effective. This submittal shall contain: a. Sufficiently detailed information to support the rationale for the change; .l b. A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint i determinations; and i t c. Documentation of the fact that the change has been reviewed and approved by the responsible Nuclear Operations Department i per CPC 2A (Quality Program). ~ i -l 6.16 RADI0 ACTIVE MATERIALS SOURCES 6.16.1.a. Each sealed source, except start-up sources subject to. core flux, containing byproduct material other than Hydrogen-3, with a half-life greater than thirty days and in any form other than gas shall be tested for leakage and/or contamination at intervals not to exceed six months. In the absence of a-certificate from a transferor indicating that a test has been made within six months prior to the transfer, the sealed source shall not be put into use until tested. j t b. Notwithstanding the periodic leak tests. required by this j condition, any licensed sealed source is exempt from such leak i tests when the source contains 100 microcuries or less of beta j and/or' gamma emitting material or 10 microcuries or less of alpha i emitting material. l a c. The periodic leak test required by this condition does not apply to sealed sources that are stored and not being used. The sources excepted from this test shall be tested for leakage prior to any use or transfer to another person unless they have been leak i tested within six months prior to the date of use or transfer. i I 6.16.2 The test shall be capable of detecting the presence of 1 0.005 microcurie of radioactive material on the test sample. The test sample shall be taken from the sealed source or from the i surfaces of the device in which the sealed source is permanently 1 mounted or stored on which one might expect contamination to accumulate. Records of leak test results shall be kept in units of microcuries and maintained for inspection by the Commission. } 91 AS PROPOSED l
l l* I 13.1 RADIOLOGICAL EFFLUENT RELEASES., l 13.1.1' RADIOACTIVE EFFLUEAT MONITORING INSTRUMENTATION ~0PERABILITY AND L SURVEILLANCE REQUIREMENTS 13.1.1.1 The radioactive effluent monitoring instrumentation channels shown j in Table 13-1'shall be Operable with their alarm / trip set points -j set to ensure that the limits of Specification 13.1.2.1 or.13.1.3.1 j are not exceeded. The alarm / trip set points of these channels -i shall be determined and adjusted in accordance with the methodology j and parameters in the Offsite Dose Calculation Manual (0DCM). l l-APPLICABILITY: At all times. 1 ACTION: t { a. With a radioactive effluent monitoring instrumentation channel i alarm / trip set point less conservative than required by the l above specification, suspend the release of radioactive effluents monitored by the. affected channel or declare the 1 channel inoperable, or change the set point so it-is I acceptably conservative. b. With less than the minimum number of radioactive effluent monitoring instrumentation channels Operable, take the action I shown in Table 13-1. Exert best efforts to return the 1 instruments to Operable status within 30 days and, if j unsuccessful, explain in the next Radioactive Effluent / Release Report why the inoperability was not. corrected. in a timely manner. 13.1.1.2 Each radioactive effluent monitoring instrumentation channel shall be demonstrated Operable by performance of the Channel Check, Source Check, Channel Calibration and Channel Functional Test l operations at the frequencies shown in Table 13-2. 1 BASES FOR 13.1.1.1 - RADI0 ACTIVE EFFLUENT MONITORING INSTRUMENTATION The radioactive effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in effluents during actual or potential releases of liquid effluents. The alarm / trip set points-for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCK to ensure that the alarm / trip will l occur prior to exceeding the limits of 10 CFR Part 20. j l 128 AS PROPOSED l
1 Table 13-3 Notation (Contd) c. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99,* Cs-134, Cs-137, Ce-141 and Ce-144.* This list does not meari that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Ef fluent Release Report / pursuant to Specification 6.9.2.2 (Administrative Controls). -6
- (LLD = 5 x 10 because of low gamma yields.)
d. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released. e A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume of a system that has an input flow during the continuous release. f. To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.
- l g.
The principal gamma emitters for which the LLD specification applies ^ exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, E Xe-133m, Xe-135 and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144** for particulate emissions. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Ef fluerit Release Report pursuant to Specification 6.9.2.2 / (Administrative Controls). -10
- (LLD = 1 x 10 because of low gamma yields) h.
The ratio of the sample flow to be sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 13.1.3.1. 13.1.4.2 and 13.1.4.3. i. Samples shall be changed at least once per 7 days and analyses shall be completed within 72 hours after changing or after removal from sampler. 138 AS PROPOSED
c. ATTACHMENT 2 CONSUMERS POWER COMPANY BIG ROCK POINT PLANT DOCKET 50-155 TECH SPEC CHANGE REQUEST EXISTING PAGES t BPOATH.JLL
ADMINISTRATIVE CONTROLS 6.9.2.1 (Contd) The annual radiological environmental operating reports shall include summarized and tabulated results of all radiological er.vironmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report. The reports shall also include the following: a summary description of the radiological environmental monitoring program including sampling methods for each sample type, a map of all sampling locations keyed to a table giving distances and directions from the reactor and the results of land use census required by the Specification 13.2.3., and results of the interlaboratory comparison program required by Specification 13.2.4. 6.9.2.2 r:r!: rel Radioactive Ef fluent Release Report E A. Radioactive Effluent Release n (c p TCd pc/ lO CFE Sb.Eg(g)(z.) A report shall be submitted to NRC " * '^-day: cfter Jeanery 1 ad kly 1 of cach yect :pecifjing the suontiti of--each-of-the- --principel redionvel44ee-celeeted-t+-encentrided-eree; in liquid end -sassou; f finanr
- d""4 -tA6-Peevi+e; 6 ;3nthi. Thi fGimet ead 8
eentent of the repner rb 11 he in accordanca virh Regul-teer- -Guid,1.21, Red:i:- 1, dawd.Jone 1994n-- 1. Caseous Effluents Cross Radioactivity Releases a. (1) Total gross radioactivity (in curies), including noble and activation gases released. (2) Harimum gross radioactivity release rate during any one-hour period. (3) Total gross radioactivity (in curies) by nuclide released, based on representative isotopic analyses performed. (4) Percent of Technical Specifications limit. b. Iodine Releases (1) Tots 1 iodine radioactivity (in curies) by nuclide released, based on representative isotopic analyses performed. 84 i i Amendment 107 February 19, 1992 TS SECTION 10
l ADMINISTRATIVE CONTROLS i 'l 6.12.1 (Contd) l c. A radiation protection qualified individual (e.g., Health Physics Technician) with a radiation dose rate monitoring device, who is i responsible for providing positive control over the activities within the area, and shall perform periodic radiation surveillance as-I specified by the Chemistry and Radiation Protection Supervisor in the RWP. 6.12.2 In addition to the requirements of Specification 6.12.1, areas accessible to personnel with radiation levels greater than 1000 mR/h at 45 cm (18 in.) from the radiation source or from any surface l from which the radiation penetrates shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Supervisor on duty l and/or health physics supervision. Doors shall remain locked except 3 during periods of access by personnel under an approved RWP which shall i specify the dose rate levels in the immediate work areas and the maximum allowable stay time for individuals in that area. In lieu of the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within i the area. For individual high radiation areas accessible to personnel with radiation l i levels of greater than 1000 mR/h that are located within large areas where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, then.that individual area shall be barricaded, conspicuously posted, and a flashing light shall be activated as a warning device. 6.13 ENVIRONMENTAL QUAllFICATION (Deleted) 6.14 PROCESS CONTROL PROGRAM (PCP) 6.14.1 Changes to the PCP shall be submitted to the Commission in the demiannual Radioactive Effluent Release Report for the period in which the change (s) was made effective. This submittal shall contain: a. Sufficiently detailed information to support the rationale for the change; b. A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and c. Documentation of the fact that the change has been reviewed and approved by the responsible Nuclear Operations Department per CPC-2A (Quality Program). / 90 Amendment 109 May 24, 1993 i
l ADMINISTRATIVE CONTROL 5-6.15 0FFSITE DOSE CALCULATION MANUAL (0DCM) l - 6.15.1 Changes to the ODCM shall be submitted to the Commission in the i E -iannua-1 Radioactive Effluent Release Report for the~ period in which
- the change (s) was made effective. This submittal shall. contain:
a. Sufficiently detailed information'to support the rationale for I the change; b. A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations; and c. Documentation of the fact that the change has been reviewed i and approved by the responsible Nuclear. Operations Department per CPC 2A (Quality Program). /' 6.16 RADI0 ACTIVE MATERIALS SOURCES l 6.16.1 a Each sealed source, except start-up sources subject.to core flux, containing byproduct material other than Hydrogen-3, with a half-life greater than thirty days and in any form other than gas shall be tested for leakage and/or contamination at intervals not to exceed six months. In the absence of a certificate from a transferor indicating that a test has been made within six months prior to the transfer, the sealed source shall not be put into use until tested. b. Notwithstanding the periodic leak tests required by this condition, any licensed sealed source is exempt from-such leak tests-when the source contains 100 microcuries or less of. beta and;or gamma emitting material or 10 microcuries or less of-alpha emitting material. j c. The periodic leak test required by this condition does not apply to sealed sources that are stored and not being used. The sources excepted from this test shall be. tested for leakage prior to any. use or transfer to another person unless they have been leak tested within six months prior to the date of use or transfer. 6.16.2 The test shall be capable of detecting the presence of 0.005 microcurie of radioactive material on the test sample. The test. sample shall be taken from the sealed source or from the surfaces of the device in which the sealed source is permanently mounted or stored on which one might expect contamination to accumul ate. Records of leak test results shall be kept in' units of microcuries and maintained for inspection by the Commission. 91 Amendment 109 May 24, 1993
l i 13.1 RADIOLOGICAL EFFLUENT RELEASES 13.1.1 RADIOACTIVE EFFLUENT MONITORING INSTRUMENTATION OPERABILITY AND SURVEILLANCE REQUIREMENTS 1 13.1.1.1 The radioactive effluent monitoring instrumentation channels shown in Table 13-1 shall be operable with their ' alarm / trip set-points i set to ensure that the limits of Specification 13.1.2.1 or.13.1.3.1 are not exceeded. The alarm / trip set points of these channels shall be determined and adjusted in accordance with the methodology and parameters in the Of f site Dose Calculation Manual -(ODCM). { l APPLICABILITY: At all times. l I ACTION: I With a radioactive ef fluent monitoring. instrumentation channeli a. alare/ trip set point less conservative than required by the I above specification, suspend the release of radioactive effluents monitored by the affected channel or declare the channel inoperable, or change the set point so it is acceptably conservative. b. With less than the minimum number of radioactive effluent-monitoring instrumentation channels Operable,' take' the action 3 shown in Table 13-1. Exert best efforts to return the instruments to Operable status within 30 days and, if unsuccessful, explain. in the next Sam @ssmoel-Radioactive -{ Effluent Release Report why the inoperability was not { corrected in a timely manner. i 13.1.1.2 Each radioactive effluent monitoring instrumentation channel shall .gf be demonstrated Operable by performance of the Channel Check. - Source Check, Channel Calibration and Channel Functional Test operations at the frequencies shown in Table 13-2. BASES FOR 13.1.1.1 - RADIOACTIVE EFFLUENT MONITORING INSTRUMENTATION / I The radioactive effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in effluents during actual or potential releases of liquid ef fluents. The alarm / trip set points for these instruments shall be calculated and adjudted in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. 128 Amendment 107 February 19, 1992 I TS SECTION 13 1
1 +. Table 13-3 Notation (Contd) The principal gaerna emitters for which the LLD specification applies c. exclusively are the following radionuclides: Mn-54, Fe-59, co-58, Co-60, 2n-65, Ho-99,* Cs-134, Cs-137, Ce-141 and Ce-144.* This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall al so be analyzed and reported in the C - -- ? Radioactive Effluent Release Report pursuant to Specification 6.9.2.2 (Administrative Controls).
- (LLD = 5 x 10-6 because of low gamma yields.)
d. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released. A continuous release is the discharge of liquid wastes of a nondiscrete e. volumel e.g., f rom 2 volume of a system that has an input flow during the / continuous release. f. To be representative of the quantities and concentrations of radioactive materials in liquid ef fluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release. g. The principal gasvaa emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135 and Ie-138 for gaseous emissions and Mn-54, Fe-59, co-58, co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144** for particulate emissions. This list does not mean that only these nuclides are to be considered. Other gama peaks that are identifiable, together with those i of the above nuclides, shall also be analyzed and reported in the S.eeinmawa4-Radiosctive Ef fluent Release Report pursuant to Specification $j 6.9.2.2 ( Administrative ' Controls).
- ( LLD = 1 x 10-10 because of low gamma yields) h.
The ratio of the sample flow to be sampled stream flow rate shall be known f or the time period covered by each dose or dose rate calculation made in accordance with Specifications 13.1.3.1, 13.1.4.2 and 13.1.4.3. i. Samples shall be changed at least once per 7 days and analyses shall be completed within 72 hours af ter changing or af ter removal from sampler. 138 i Amendment 107 February 19, 1992 TS SECTION 13}}