ML20245E063
| ML20245E063 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 02/19/1987 |
| From: | Julie Ward SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Marsh R NRC OFFICE OF INVESTIGATIONS (OI) |
| Shared Package | |
| ML20245E058 | List: |
| References | |
| FOIA-89-2, FOIA-89-A-7 JEW-87-160, TAC-64735, NUDOCS 8811110154 | |
| Download: ML20245E063 (28) | |
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EACRAutNTo MuNCPAL UT1UTY otSTRici C P. O. Box 158 . a rakento CA 95852 1830.19161 452 3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA 19 FEB 27 PP.1: 42-February 19, 1987 D,,t n,l D.
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t R. Marsh, Director i;!I"k/l' Office of Investigations, Region V ./D U. S. Nuclear Regulatory Conrnission 4 I 1450 Maria Lane, Suite 210 C' - 'L ~
Walnut Creek, CA 94596 00CKET NO. 50-312 1.! CENSE NO. OPR-54 Off1CE Of INVESTIGATION INQUIRY
Dear Mr. Marsh:
The Sacramento Municipal Utility District has thoroughly reviewed the matters of your December 24, 1986 request for additional information regarding your inquiry into the operations and rt.anagement of the Rancho Seco Nuclear ,
Generating Station's liquid effluent program. Enclosure I provides our response to your request for additional information.
We consider that the submittal of this response completes our ef forts to provide the inforenation requested in your December 24, 1986 letter.
If there are any questions concerning this report, please contact Mr. R. Ashley at (916) 452-3211, extension 4475. ,
Sincerely, i
iD in E. Ward x A M Deputy General Manager, Nuclear m cc m en n 3.8. Martin, NRC, Walnut Creek i; U 550 ec:
l Sydney Miner, NRC, Bethesda 2:
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o Tony D'Angelo, NRC, Rancho Seco DF/dr ,cg i .i
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-. ENCLOSURE I I
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RESPONSC TO NRC REQUEST FOR INFORMATION REGARDING THE LIQUID EFFLUENT PROGRAM i
Recuest 1 ,
l Provide copies of pages 2-6 through 2-9 and page 2-11 of Reference 6-Appendix
- 1. Evaluation Report Rancho Seco Nuclear Generating Station. TERA Corporation, June 1, 1976.
Response 1
.Three complete copies,of the Appendix ! Evaluation Report, dated June 1.1976, are attached.
Reauest 2 Provide procedures that were established between January 1980 to Present regarding:
A.10-Demineralized Reactor Coolant Storage System A.17-Miscellaneous Liquid Radwaste System
/ A.28-Miscellaneous Water Systems Plant Operations Manual Procedures that are related to A.10. A.17 and d.28.
- Temporary procedures established for transferring liquid ef fluents from the Demineralized Reactor Coolant Storage Tank (DRCST) and Miscellaneous Waste Holdup Tank (MWHUT) to the Radwaste Holdup Tank (RHUf).
Response 2 The requested procedures are attached, h
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, Recuest 3
- Provide'the sampling analysis results obtained from the completion of
( procedure AP.306 Sanpling Points, Analysis Required.. frequency and Specification Levels for the period of January 1980 to Present. Restrict the data to the following:
111-D Component Cooling Water III-E Demineralized Storage Tank filter Outlet, RC13
!!!-E Demineralized Reactor Coolant Storage Tank III-F Miscellaneous Water Holdup Tank (T0993) '
III-F Miscellaneous Waste Tank (T-667) .
If any samples were not obtained, please explain the reason the samples were not taken.
Response 3 Sample results are attached.
Per AP.306-!!!-F, the Miscellaneous Waste Tank is only required to be sampled if it is feeding the Miscellaneous Waste Evaporator. For the period of time referenced in Request 3 and prior to that time, the contents of T-667 were not fed to the Evaporator, therefore no samples were obtained and no data are
-available.
Recuest 4 Provide an explanation of all events and facts concerning Rancho Seco's
( unplanned modifications for partial draining of the DRCST and MWHUT to the RHUT. Include all supporting data such as ECN's, Work Requests and Nonconformance Reports. Your explanation should describe all occurrences that-caused the modifications, a description of exactly what the modifications were, the dates each modification was in effect and a description of any I analyses that were conducted concerning the causes and prevention of reoccurrences of the modification Response 4_
Each temporary modification to allow the transfer of water from the DRCST and g MWHUT to the RHUTs was implemented to reduce the inventory of reprocessed waste water occurring during periods of primary to secondary OTSG tube leakage. These were necessary due to operational capacity restraints.
A review of historical plant records identified the following documentation related to this operational evolution (as attached):
- 1. Work Request No. 508173, dated December 6,1975, documenting the removal of a temporary hose between the DRCSi and the RHUT on April 6, 1975. No work request was located documenting installation.
- 2. Work Request No. 57111, dated May 20, 1981- documenting the installation of portable pump and PVC piping between the MWHUT and the RHUI on May 21, 1981.
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' 3. Work Request No. 57038, datcd July 7,1981, documenting the removal of PVC
,- piping from the RHUTS on August 3,~1981.
b 4. Work Request No. 67251, dated November 20, 1982, documenting the installation of a pump and PVC pipir.g Detween Pi.S-158 drain valve on the DRCST and the RHUTs on December 2,1982. A work request was not located for the removal of this temporary piping and pump, but inspection indicates this was-indeed accomplished.
- 5. W9rk Request No. 117951, dated August- 13, 1986, documenting the connection
- of PVC piping between the RHUTs and DCRST. .
- 6. Temporary change to procedure A.10. Demineralized Reactor Coolant Storage System, approved on January 3,1986 to allow pumping DCRST to RHUTs.
- 7. Temporary change to procedure A.10, approved September 18. 1986, allowing-the transfer of water from DCRST to RHUIs.
Si Procedure change to procedure A.10, approved October 9, 1986, voiding the temporary change dated September 18, 1986.
- 9. Temporary change to procedure A.10, approved October 10, 1986, allowing the transfer of water from the DRCST to the RHUTs. .
- 10. Procedure change to procedure A.10, approved October 28, 1986, voiding the temporary change dated October 10, 1986.
The documentation identified during this review does not provide a complete
{ record of operational actions to reduce DRCST/MWHUT inventories by transferring water to the RHUTs. This is indicated by our review of liquid eff1 bent release data. DRCST water is tritiated, therefore, periods of increased monthly effluent releases of tritium indicate operational actions to reduce DRCST inventory by transferring this tritiated water to.the RHUTs.
The following are periods of increased ef fluent releases of tritium (graphs and release totals are attached).
- 1. September - October, 1975
- 2. May - June 1981
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- 3. November - December, 1982
- 4. february - March, 1983
- 5. July 1984 - March 1985
- 6. June 1985
- 7. September 1985
- 8. January March, 1986 3
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'- Our efforts to 1ccate missing plant documentation regarding the transfer of e DRCST and MWHUT water to the RHUTs have been extensive. However, we have been unable to locate all of the information requested. j
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l . Presently, the' temporary piping is disconnected and a permanent design
- modification per ECN R0775 (as attached) is planned which will install a line between the discharge of the DRCST pumps (P-622 A&B) and the RHUTs.
Request 5 With respect to number 4 above, provide describe the sampling requirements for the modifications and the results of any sampling of the modified systems that were conducted prior to, during and after drainage of the tanks.
Response 5 .
Histor'1cally, the sampling / analysis program was not modified for this operational evolution. Plant ef fluent control continued at the RHUTs (i.e., each plant release from the RHUTs was sampled in accordance with the estabitsbed program to control the release of radiological effluents as identified in our response to question 4 of your July 18, 1986 inquiry).
Recuest 6 Provide copies of the data for the period 5/26/77 - 5/21/8) concerning reference 21 - Computer Compilation of Release Permit Data, October 14, 1974
( through October 28, 1986. ,
Response 6 The data supplied here supplements that transmitted as reference 21 of the original response to question 6 of the NRC Office of Investigation Letter dated July 18, 1986. As indicated on page 23 of our previous response, The search the for five Release Permit records for the year 1980 were not found.
these records is continuing; however, they have not yet been located (an Occurrence Description Report No. 584 (attached) was filed describing the missing records). Although the five Release Permits for the year 1980 are missing, the data for retention basin releases are available and a compilation f
of the radioactivity released was reported in the annual report for 1980 (reference 14 of our previous response). As indicated in reference 14 of our previous response, there were no radioactive releases for the years 1978 and 1979. Since documentation has not been located for the five releases nade in 1980, only six Release Permits, gener;ated between May 26, 1977 and May 21,1981 are attached. One radioactive request was nede in 1977 (5/26/77). The remaining five Release Permits were all in 1981 and occurred between the dates 5/18/81 and 5/21/81.
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Recuest 7 o
(i Provide data collected for the period of January 1980 to Present concerning ,
procedure MEG 303, Site Radioactive Water Inventory. If any samples were not i obtained, please explain the reason the samples were not taken. I Response 7 MEG 303 Site Radioactive Water Inventory, is a calculation of inventory and J I
not sample based. MEG 303 and inventory data sheets are attached.
Reauest 8 From initial plant startup to July 20, 1984, supply the LLD/MDA values used prior to implementation of the Radiological Environmental Monitoring Program (REMP).,
Response 8 The attached is an excerpt from the original Appendix B of the AEC approved Technical Specifications. As indicated in section 2.6.1.0 (Page 10) and '
j Table 2.6-.1 (page 20), the Technical Specification values for 1.t.0/MDA for gamrna emitting isotopes (untti the formation of the REMP), was SE-7 uC1/ml.
- .This value for isotope concentrations was used until the implementation of the REMP in July, 1984.
Reauest 9
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Provide dates that fish sampling was first initiated in Clay Creek. Supply supporting documents and related procedures.
Response _9 rish samples were first collected from Clay Creek on the following dates:
April 11, 1984 bluegill sunfish April 12,1984 black bass catfish April 26, 1984 bluegill large mouth bass catfish The April 11, and April 12, 1984 samples were sent to the District's environmental contractor (CEP) for analysis. The results were included in their second quarter 1984 report to the District. The CEP report is attached.
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4 Recuest 10'
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(' Provide ' copies.of internal and. external audits /survet tlances of the
- Radiological Environmental Monitoring Program for the period 1980 to Present.
Include supporting documents concerning corrective actions taken in response 1
.to identified deficiencies. l Response 10 External audits of the Radiological Environmental Monitoring Pr,ogram were
_ previously provided as references 7 through 13 of our response to your
.JulyL18,.1986 inquiry. Internal Quality Assurance audits and surveillance are attached.
Recuest 11 .
Provide a description of the Sacramento Municipal Utility District's Radiological Environmental Monitoring Program organization from the initiation of plant.startup to present, include names of individuals and their responsibilities from both the corporate and station organizations.
Response 11
'The organizational structure of management at Rancho Seco Nuclear Generating Station (RSNGS) is described in procedure AP-1. A complete revision history of this procedure has been included (as Enclosure 1 to Response'11) for informational purposes. Two lists are attached to the revision history. The first'11st simply indicates the revision dates and the position titles ,
( affected by that revision. Only positions relating to Radiation Protection and Environmental programs are included on this list. If a revision did not ef fect any changes in jobs related to environmental monitoring, titles' were not added (however, the revision and the effective dates are included). The i
second Itst shows the same information, but sorted in alphabetical order of Job Title.
Included as Enclosure 2 to Response 11 are the organizational structures outlined in procedure AP.1. These structures fall into four separate outlines, separated by the revisions which caused a change to either the structure or position descriptions in the current structure. Ileadings for
[ each of the four structures indicate which revisions relate to that structure and the dates for which that organizational structure was effective, by reviewing-the specific procedure revision for a time period, specific job responsibilities can be determined. Procedure AP.1 is not designed to give a -'
description of every position on site and, as such, there have occasionally been positions in between those described in AP.I. The third and fourth pages of the organizational structures indicate such positions as they occurred and the time periods during which the charts were effective. (for instance, the position of Assistant Chem / Rad Supervisor was not described in AP.1 but was a ,
position in the organtrational structure).
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- Also included with the organizational structures are the names of the l
~, personnel that held those positions (for the indicated time periods). As there are four distinct organizational structures, each corresponding to
( different procedure revision histories, there are four corresponding lists of-L personnel filling the positions (as described-in AP.1). Also included is a current organizational chart and a list of personnel filling the positions related to environmental monitoring. This information indicates the on site environmental programs related personnel.
The corporate responsibilities have not been outlined in procedures (as many of the on-site positions are). The information supplied as Enclosure 3 to Response 11 indicated the results of information gathered from interviews with personnel regarding the structure and personnel associated with the corporate environmental monitoring programs The organizational charts and the names on these charts are compilations of this information. The primary information regarding responsibilities can be ascertained from the position title.
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RANCHO SECO UNIT 1 1
TECHNICAL' SPECIFICATIONS Limiting Conditions 'for Operation-g ' 3.17. 2'- ' Dose The ' dose 'or dose corx11tment to a member of the' public frca radioactive materials in liquid ef fluents released beyond ther site boundary shall. be. limited:
( a. During any calendar quarter to 1.5 arem to the total body and to 5 mrem.to any organ; and During. any calendar year to 3 mrem to the ' total body and to_10l
- b. . ' arem to any organ.
Applicability- At all times Action
- a. llith the calculated dose or dose commitment from the release of:
.- radioactive materials in liquid effluents exceeding any of' the above limits, prepare and submit to the Commission within 30 .,.-
days a Special Report. This Report will identify the cause(s).
for exceeding the limit and define the corrective actions to be taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in
' compliance with the above limits.
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This specification is provided to impienent the requirements of Sections II.A, III.A and IV. A of Appendix I,10 CFR Part 50. The Limiting Condition for ;
Operation implements the guides set forth in Section II.A of Appencix I. The ,
I j ACTION statements provide the required operating flexibility and at the same-time implement the guides set forth in Section IV. A of Appendix I to assure that' the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable." The dose calculations in the ODCM implement .
the requirements in Section III.A of Appendix I that confomance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the' actual exposure of an individual through appropriate path-ways is- unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology l provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from
.4outine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine' Reactor Releases for the Purpose of Implementing Appendix I," April ,
1977. i Amendment No. 53
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.17.3 Liouid Holduo Tanks The quantity of radioactive material contained in each of the following tanks shall be limited to less than or equal to 10 Curies, excluding tritium and dissolved or entrained noble gases:
- a. Regenerant Holdup Tanks
- b. Outside Temporary Tanks , . ,
Applicability At all times ]
Action With the quantity of radioactive material in any of the listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit, and describe the events leading to .
this condition in the next Semiannual Radioactive Effluent Release Report.
Bases !
i Restricting the quantity of radioactive material contained in the specified outdoor tanks provides assurance that in the event of an uncontrolled release of the contents, the concentration at the nearest surface water supply in an unrestricted area would be less than the limits of 10 CFR 20, Appendix B, Table II, Column 2. There I
.are two Regenerant Holdup Tanks. The limit applies to each tank '
individually.
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Amendment No. 53 3 72
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Liaiting Conditions for Operation l 3.25 FUEL CYCLE DOSE ..
The annual dose or dose corraitment to a acaber of the public due to releases of radioactivity and radiation from uraniua fuel cycle sourtes is limited to < 25 area to the total body or any organ (except the thyroid, which is limited to
<75 area).
Applicability At all times. ,
s Action With the calculated doses from the release of radioactive caterials in liquid or gaseous effluents exceeding twice the limits o f Specification.s 3.17.2.a , 3.17.2.b , 3.18,1.a , 3.18,1.b, 3.18.2-.a ,' 3'.18.2.b , 3.18.3.a . or 3.18.3.S. cal cul a tions shoul d be made to detertaine whether the above limits of Specification 3.25 If such is the case, prepare and, submit to ,
have been exceeded. i the Commission within 30 days, a Special Report that defines the corrective action to be taken to reduce subsequent releases to
- prevent recurrence of exceeding the above limits and includes the schedule for achieving confornance with the above limits.
This Special Report, as defined in 10 CFR Part 20.405(c), shall include an analysis that esticates the radiation exposure (dose) to a MEMBER OF THE PUBLIC f rom uranium fuel cycle sources, including all effluent pathways and direct radiation, for the '
calendar year that includes the release (s) covered by this i repo rt. It shall also describe levels of radiation and !
concentrations of radioactive caterial involved, and the cause of the exposure levels or concentrations. If the esticated !
j dose (s) exceed the above limits, and if the release condition '
resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provision of 40 CFR Part 190.
Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is ,
complete.
Bases This specification is provided to aeet the dose limitations of 40 CFR 190. I The specification requires the preparation and subaittal of a Special Report whenever the calculated doses froa plant radioactive effluentsSeco For the Rancho exceed twice site,it is the design objective doses of Appendix I.
highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC uill exceed I the dcse limits of 40 CFR 190 if the plant remains within the reporting r requirement level. The Special Report will describe a course of action which !
should result in the limitation Forof thethe annual purposes dose of the to aReport, Special 11 EMBER it lOF to within the 40 CFR 190 liaf ts.
may be assumed that the dose corraitaent to the MEMBER OF THE PUBLIC from oth : i Uraniua fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the If the dose same to any site orOF MEMBER within a radius of 5 miles must be considered.
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t' RANCHO SECO UNIT.1 ,
L TECHNICAL SPECIFICATIONS.
Limiting Conditions;for.0perat'on f
8-i 3.25 (Continued)'
Bases- .(Continued)
.THE PUBLIC !1s estimated to exceed the_ requirements- of 40 CFR 190. the Special:
' Report,. with a request for a _ variance (provided the' release conditions resulting in violation of 40 CFR 190 have not already been corrected), in -
accordance with the provisions of 40 CFR 190.11:is considered to be a timely 4
request and fulfills the requirements of 40 CFR 190 until NRC- staff action is.
completed.- An individual is 'not; considered 'a member of- the public' during any period in'which he/she:is engaged in carrying out any operation which' fi part'
..of the' nuclear fuel cycle.
4 Amendment'No. E3,87 3-91
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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards
- 4. 21 LIQUID EFFLUENTS ,
- 4. 21 . 1 Concentration Surveillance Recui rements The concentration of radioactive caterial at any tiae in liquid effluents released from the site shall be continuously,conitored in accordance with Table 3.15-1.
r . c The liquid effluent continuous conitor having provisions for automatic termination o'f liquid releases, as listed in Table 3.15-1, shell be used to limit the concentration of radioactive caterial released at any time from the
?te to areas beyond the site boundary to the values given in Specification.
3.17.1.
The radioactivity content of each batch ~ of radioactive liquid waste 'to be di,scharged shall be determined prior to release by sampling and analysis in accordance with Table 4.21-1. The results of pre-release analyses shall be used with the calculational methods in the ODCM to assure that the concen- !
tration at the point of release is limited to the values in Specification 3.17.1.
Post-release analyses of samples frca batch releases shall be performed in accordance with Table 4.21-1. The results of. the post-release analyses shall be used with the calculational methods in the ODCM to assure that the concen-
---trations at the point of release are limited to the values in Specification 3.17.1.
Bases This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to areas beyond the site boundary will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II. This licitation provides additional assurance that the levels of radioactive caterials in bodies of water outside the site vill not result in exposures within: (1) the Section II.A Design Objectives of Appendix I,10 CFR Part 50, to an individual, and (2) the limits of 10 CFR Part 20.106(e) to the population. The concentration limit for noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological P,rotection (ICRP) Publication 2.
There are no continuous releases of radioactive or potentially radioactive liquids f rom the plant. All releases f rom the plant are by batch method.
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i Amendment No. 53 4- 69 j l
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j RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS
.( Surveillance Standards TABLE 4.21-1 i RADI0 ACTIVE LIOUID llASTE SAMPLING AND ANALYSIS PROGRAM I].
b Sampl i ng - flininua Analysis Type of Activity Lower Limit Liquid Release Type Freque ncy - Frequency Analysis Of Detection I (LLC)
(uCi/n1)(a) !
Each Batch Each Batch Mn-54, Fe-59, 5 x 10-7 A..Batchllaste(Ra-lease Tanks bl Co-58, Co-60 P P Zn-65, Mo-99, Cs-134, Cs-137 Ce-141, and Ce-144 '
(c) l I -1 31 1 x 10- 5 One Batch /M M Dissolved and 1 x 10- 5 Entrained Gases I (Gamma Emitters)
M Each Batch Composite (d) H-3 1 x 10- 5 P
Gross Alpha 1 x 10- 7 0 (d)
Each Batch Composite Sr-89, Sr-90 5 x 10- B P
f A
Amendment No. 53 4-70 1
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. RANCHO SECO UllIT 1
.TECHN2 CAL SPECIFICATI0i15 .
E Surveillance Standards TABLE L 4.'21 -1 (c onti nued)
Table flotation
- l. a. /The lower limit of detection (LLD) is defined'in the:0DCli.
- b. A batch miease is the discharge of liquid wastes of discrete volume..
Prior,to sampling, each batch willbe isolated and thoroughly mixed,4 to assure representative sampling.
- c. Other. peak's which are measurable and identifiable', together with the .
listed nuclides, shal1 also be identified and reported.- Nuclides which are below the LLD. for the analysis should not.be reported as-being present at the LLD level.
.d. A composite sample is one in which the quantity of liquid sample's is proportional to the quantity of liquid waste discharged ~and in which the
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- method'of sampling employed results _ in a specimen which is representative
' of the , liquids released.-
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Amendment flo. 53
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RANCHO SECO UN1T 1 TECHNICAL SPECIFICATIONS ,
l '
l Surveillance Standards
- 4. 21 . 2 Doses Dose Calculations -' -'
Cumulative dose contributions from liquid effluents shall be de+ ermined in accordance with the Offsite Dose Calculation Manual (00CM) at least monthly.
Bases s - 4 This specification is provided to implement the' requirements of Sections II. A, III. A, and' IV. A of Appendix I,10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operating flexibility and, at the same time, implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "a:;
low as reasonably achievable." The Dose Calculations Methodology'in the'00CH 1mplements the requirements in Section III. A of Appendix.I .that conformance .. ..
with' the guides of Appendix I is to be shown by calculational procedures based on models-and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The .
equations specified in the 0004 for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent uitt !
the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977, and Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents f rom Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix 1," April 1977.
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% I Amendment No. 53 4 72
RANCHO SECO UNIT 1
- i. TECHNICAL SPECIFICATIONS l
Surveillance Standards'
- 4. 21 . 3 Licuid Holduo Tanks
- l The cuantity of radioactive caterial contained in each tank listed in Specification 3.17.3 shall be determined to be within the specified limit b'<
analyzing a representative sample of the tank's contents at least weekly.whhn radioactive materials are being added to the tank.
Bases 4
Restricting the quantity of radioactive material contained in the specified -
outdoor tanks'provides assurance that in the event of an uncontrolled release of the conte'nts, the concentration at the nearest surface water supply in an unrestricted area would be less than the limits of 10CFR Part 20, Appendix B, Table II, Column 2.
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- Tanks included in this specification are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system.
Amendment No. 53
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RANCHO SEC0 UNIT-'!.
TECHNICAL SPECIFICATIONS Administrative Controls 6.7' SAFETY LIMIT-VIOLATION 6.7.1 The:following actions shall be taken in the event a Safety Limit is violated:
- a. The provisions of 10 CFR 50.36 (c) (1) (i) shall be compliec with immediately.
- b. The Safety Limit Violation shall be reported immediately to the '
Plant Superintendent, the Manager of Nuclear Operations, the Chairman.of the MSRC and to the Conynission,
- c. A Safety Limit Violation Report shall be prepared. The report' shall be reviewed by the PRC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence..
- d. The Safety. Limit Violation Report shall be submitted to the .
Commission, the MSRC. the Manager of Nuclear Operations and the Plant Superintendent within 10 days of the violation.
6.8 -PROCEDURES 6.8.1 Written procedures shall be established. implemented and maintained .
covering the activities referenced below:
- a. The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, November 1972.
- b. Refueling operations.
- c. Surveillance and test activities of safety related equipment.
- d. Security Plan implementation. *
- e. Emergency Plan -implementation.
- f. Fire Protection Procedures implementation.
- g. Process control program implementation.
Offsite Dose Calculation Manual implementation.
h.
- i. Effluent and environmental quality control program.
6.8.2 Each procedure and administrative policy of 6.8.1 above, and chanues thereto, shall be reviewed by the PRC. Those matters pertaining to items 6.8.la, b, c, g, and h, above shall be approved by the Plant Superintendent prior to implementation and reviewed periodically tis set forth in each document. The manager of Nuclear Operations, shi.ll also approve Security Plan and Emergency Plan implementing procedures.
6.8.3 Temporary changes to procedures 6.8.1 above may be made provided:
- a. The intent of the original procedure is not altered.
Amendment No. Js!.7/,53,87 , 6-11
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS-l
~
Administrative Coatrols 6.8 PROCEDURES (Continued)-
- b. The change is approved by two' members .of the plant' managerrent staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.
.c.- The change is documented, reviewed by the PRC and approved by the Plant Superintendent within seven (7) days of implementation.
6.9 REPORTING RE0VIREMENTS 6.9.1 In addition to the applicable reporting requirements of Title 10 Code of Federal Regulations, the following reports shall be submitted to the 01 rector of the Regional Office of Inspection and Enforcement unless otherwise noted.
.Startup Report
.6.9.1.1 A sumary report of plant startup and power escalation testing. shalls be submitted following (1) Receipt of an operating license; (2) amendment to the license involving a planned increase in power level; (3) installation of fuel that has a different design or has bee.1-manufactured by a different fuel.~ supplier; and (4) modifications that may have significantly altered the nuclear, themal or hydraulic performance of the plant. The report shall address each of the tests identified in the FSAR and shall include a description of the i measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective act ons that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license
-conditions based on other comitments shall be included in this report.
6.9.1.2 Startup reports shall be submitted within (1) Ninety (90) days following completion of the startup test program; (2) Hinety (9C) days following resumption or commencement of comercial power operation; or (3) Nine (9) months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program and resumption or commencement of comerical power I operation), supplementary reports shall be submitted at least every three (3) months until all three events have been completed.
Amendment No. U ,87 , 6-12 i
V
- f f RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls 6.9.2 ENVIRONMENTAL REPORTS 6.9.2.1 Annual Radiological Reports Annual reports covering the activities of the unit, as described below, for the previous calendar year shall be submitted prior to
,. March 1,of each year following initial criticality.
Reports required on an annual basis shall include:
A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated man rem exposure, according to work and job functions,* e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste
. processing, and refueling. The dose assignment to various duty functions may be estima tes based on pocket dosimeter, TLD, or
- film badge measurements. Small exposures, totaling less than .
20% of the individual total dose, need not be accounted for. In the aggregate, at leas t 80" of the total whole body dose received from external sources shall be assigned to specific major work s, functions.
6.9.2.2 Annual Radiological Environmental 00eratino Report 6.9.2.2.1 Routine radiological environmental operating reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year. The initial report shall be submitted prior to May 1 of the year following initial criticality.
5.9.2.2.2 The annual radiological environmental operating reports shall include summaries, interpretations, and statistical evaluation of the results of the radiological environmental surveillance activities for the !
report period, including a comparison with preoperational studies, j operat'16nal controls (as appropriate), and previous environmental '
surveillance reports, and an assessment of the observed impacts of the plant operatiori on the environment. The reports shall also include the results of the land use censuses. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.
l
{
"This tabulation supplements the requirements of s20.407 of 10 CFR Part 20. {
I s ,
Amendment No. }J', 53 6-123 1
~
RANCHO SECO UNIT 1-TECHNICAL SPECIFICATIONS-6.9.2.2.2 (Continued)
The annual radiological ' environmental operating reports shall include sumarized and tabulated results of all. radiological-environmental samples taken during the report period. In tie event that some results are not available for inclusion witi 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 sumary description of the radiological environmental monitoring program; including sampling methods for each sample type, size and physical characteristics of each sample type, sample preparation ;
methods, analytical methods, and measuring equipment used; a map of all sampling locations keyed to a table giving distances and directions from one reactor; the result of land use censuses, and the results of licensee participation in the Interlab Comparison '
Program. The ' annual report shall also include infomatiLn ~ ,
related to Specification 4.29. '
6.9.2.3 Semiannual Radioactive Effluent Release Report-Routine radioactive effluent release reports covering.the operation of the 'Jnit during the previous six months of operation shall be submitted within 60 days af ter January 1 and July 1 of each year. The period of the first report shall begin with the date of initial c riticality.
6.9.2.3.1 The radioactive effluent release reports shall include a sumary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21 " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," with data sumarized on a quarterly basis, following the format of Appendix B thereof.
The radioactive effluent release reports shall include the release of gaseous effluents during each quarter, as outlined in Regulatory Guide 1.21, with the data sumarized on a quarterly basis, following the fomat of Appendix B thereof. A sumary of meteorological conditions during the release of gaseous effluents will be retained on-site for two years. In addition, any cranges to the Offsite Dose Calculation Manual will be submitted with the Semiannual Radioactive Effluent Release Report.
i Amendment No. E3,87 6-12b l
fi
'i RANCHO SECO UNIT 1 a 3 ,
TECHNICAL.SPECIFICAT!ONS ,,
l L Administrative Controls
/ 4
- 6. 9. 2. 3.1 (continued)
The~ radioactive effluent release reports shall include an assessm.ent
- ' of the radiation doses from radioactive effluents to individuals due to their activities inside the site boundary during.the report period.
' - All assumptions used,in making these assessments (e.g., specific activity, exposure time, and location) shall be included in these reports.
I' The radioactive effluent release reports shall include the following.
information for all unplanned releases to unrestricted areas of radio-
. active materials in gaseous and liquid effluents:
- a. - A description of the event and equipment involved,
- b. Cause(s) for the unplanned release.
- c. Actions t,aken to prevent recurrence.
.. , d. Consequences of the. unplanned release.
The radioactive effluent release reports shall include an assessment.
of radiation doses from the radioactive liquid and gaseous effluents released from the unit during each calendar quacter, as outlined in Regulatory Guide 1.21. The releases of effluents shall M used for I determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the Offsite Oose Calculation Manual (ODCM).
The radioactive effluent release reports shall it.clude any changes te the PROCESS CONTROL PROGRAM (PCP) or (ODCM) made during the reporting
. period, as provided in Specifications 6.14 and 6.15, 6.9.3 Monthly Report Routine reports of operating statistics, including narrative sumary of operating and shutdown experience, of lifts of the Primary System Safety Yalves or EHOVs, cf: major safety-related maintenance, and tabulations of facility changes, tests or experiments required pursuant to k 10 CFR 50.59(b), shall be submitted on a monthly basis to the Office oD Management Information and Program Control, U.S. Nuclear Regulatory Comission, Washington, D.C. 20555, with a copy to the Regional Office, postmarked not later than the 15th day of each month following the calendar month covered by the report.
.LICEN!EE EYENT REPORT 6.9.4 The LICENSEE EVENT REPORTS of Specification 6.9.4.1 below, including corrective actions and measures to prevent recurrence, shall be reported to the NRC as Licensee Event Reports. Supplemental reports- Ir may be required to fully describe final resolction of occurrence.
case of Corrected or supplemental reports, a License Event Report
.' shall be completed and reference shall be made to the original report date, pursuant to the requ4rements of 10 CFR 50.73.
Amendment No.' 77, /f, U, 63 6-12c
g'y x
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Q-a N :+ a'n L SACIL iENTO MUNICIPAL' UTILITe JISTRJCT' " -
j OFFICE MEMORANDUM -
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FaoMi George' Campbell-
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