ML19317G789
| ML19317G789 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 08/18/1977 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19317G754 | List: |
| References | |
| NUDOCS 8004010618 | |
| Download: ML19317G789 (10) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUpp0RTING AMENDMENT NO. 12 TO FACILITY OPERATING LICENSE NO. DpR-54 SACRAMENTO MUNICIPAL UTILITY DISTRICT RANCHO SECO NUCLEAR GENERATING STATION DOCKET NO. 50-312 Introduction By letter dated June 21, 1977, the Sacramento Municipal Utility District (the licensee) requested changes to the Technical Specifications appended to Facility Operating License No. DPR-54 for the Rancho Seco Nuclear Generating Station (the facility).
The proposed amendment would make minor changes in Sections 3.3, 4.1 and 5.41 of Appendix A, would remove pages from Section 4.10 of Appendix A that are already in Appendix B, would correct a typograph-ical error in Section 2.5.c of Appendix 3, and would clarify Section 2.6.2.E of Appendix B.
Evaluation Following is our evaluation of each of the proposed changes:
Appendix A, Section 3.3 - In the bases to this section, the peak clad temperature limit would be changed from 23000F to 22000F. This is consistent with Section 50.46(b)(1) of the Code of Federal Regulations.
The Emergency Core Cooling System analysis for the facility also correctly used 22000F as the limit for peak clad temperature. Thus, we find the change acceptable.
Appendix A, Section 4.1 - A fluoride limit is given in Section 3.1.5, but there is no sampling schedule. This change would require monthly sampling of fluoride. We find this acceptable.
Appendix A, Section 4.10 - Page 4-42a (Table 4.10-2) and Figure 4.10-1 are duplicated in Appendix B.
We agree that they belong in Appendix B and thus find their removal from Appendix A acceptable.
Appendix A, Section 5.4.1 - This change would allow the licensee to either store new fuel after inspection in the new fuel dry storage rack or the spent fuel storage pool. The new fuel dry storage rack R004016[/@
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is used to temporarily store new fuel prior to being placed in the pool. This change would allow new fuel to be placed in the pool without first placing it in the dry storage rack. We find this acceptable.
Appendix B, Section 2.5.c - There was a typographical error in this section allowing 2 lbs/ day of dissolved zine in effluent water wh'en averaged over 30 days.
It should allow 12 lbs/ day when averaged over 30 days as specified by the State of California Regional Water Quality Control Board, Central Valley Region.
Appendix B Section 2.6.2.E - We have reviewed the Rancho Seco design and have detemined that continuous monitoring and recording of the liquid waste flow is not required before the dilution of the waste. The liquid waste flow is continuously monitored and recorded after dilution, and there is an additional flow indicator (with recording) before dilution.
Provided the operator manually records the flow rate before dilution, we conclude that the plant design for flow monitoring conforms with Regulatory Guide 1.21 and the amerdment is acceptable.
Environmental Consideration We have determined that the amendment does not authorize a change in effluent types or total amounts nor an increase in power level and 1
will not result in any significant envimnmental impact. Having made l
this detemination, we have further concluded that the amendment l
environmental impact and, pursuant to 10 CFR 551.5(d)(4) point of involves an action which is insignificant from the stand
, that an l
environmental impact statement or negative declaration and environ-mental impact appraisal need not be prepared in connection with the issuance of this amendment.
Conclusion We have concluded, based on the considerations discussed above, that:
(1) because the amendment does not involve a significant increase in 1
the probability or consequences of accidents previously considered and does not involve a significant decrease in a safety margin, the amendment does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and I
(3) such activities will be conducted in compliance with the Comission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Dated: August 18, 1977 l
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ATTACHMENT TO LICENSE AMENDMENT NO. 12 FACILITY OPERATING LICENSE NO. DPR-54 DOCKET NO. 50-312 Revise Appendix A as follows:
Remove Pages Insert Pages Page 3-22 Page 3-22 Pages 4-9 & 4-10 Pages 4-9 & 4-10 Page 4-42a Figure 4.10-1 Section 5.4 Page 5-6 Revise Appendix B as follows:
Remove Pages Insert Pages 7&8 7&8 11 & 12 11 & 12 Changes on the revised pages are shown by marginal lines. Pages 4-10, 7, and 12 are unchanged and are included for convenience only.
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s RANCHO SECO UNIT 1
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TECHNICAL SPECIFICATIONS Limiting Conditions for Operation
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In the event that the need for emergency core conling should occur, function-ing of one train (one high pressure injection pump, one decay heat removal pump, and both core flooding tanks) will protect the core and in the event of a main coolant loop severence', limit the peak clad temperature to less than 2,200 F and the metal-water reaction to less than 1 percent of the clad.
l; The nuclear service cooling water system censists of two independent, full capacity,100 percent redundant systems, to ensure continuous heat removs1.(3}
REFERENCES (1) FSAR, paragraph 6.2.1 (2) FSAR, paragraph 9.5.2 (3) FSAR, paragraph 9.4.1
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f F22 Amendment No.
12
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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards TABLE 4.1-3 MINIMUM SAMPLING FREQUENCY Item Check Frequency Radio-chemical analysis ( }
M 1.
E determination (5)
Semiannually b.
Gross activity (l) (3) 3/ week c.
Tritium radioactivity M
d.
Chemistry (Cl and 0 )
3/ week 2
e.
Boron concentration 2/ week l
f.
Fluoride M
2.
Borated water storage Boron concentration M and after each tank water sample makeup 3.
Core flooding tank Boron concentration ( )
M and after each water sample makeup 4.
Spent fuel storage Boron concentration M and after each water sample
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makeup Gross activity ((2)(3)
Weekly 5.
Secondary coolant a.
Iodine analysis Weekly b.
6.
Concentrated boric Boron concentration 2/ week and after acid tank each makeup 7.
Waste gas decay Isotope analysis Q Prior to tank release
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8.
Auxiliary Building Isotope analysis W
plant vent 9.
Spray additive tank NaOH concentration ( }
Q and after each makeup 10.
Purge vent Gross activity During each purge 11.
Blowdown from cooling Gross activity ( )
M toven (1)When radioactivity level is greater than 20 percent of the limits of Technical Specification 3.1.4, the sampling frequency shall be increased to a minimum of once each day.
(2)When gross activity increases by a factor of two above normal, an iodine analysis will be made and performed thereaf ter when the gross activity increases by ten percent.
(3)Not performed during cold shutdown (4)When activity level exceeds ten percent of the limits of 10CFR20, the sampling frequency shall be increased to a minimum of once each day.
(5)E determination will be started when gross beta-gamma activity analysis j
inoicates greater than 10 pCi/ml and will be redetermined each 10 Ci/ml increase in gross beta-gamma activity analysis. A radio chemical analysis for this purpose shall consist of a quantitative measurement of 95% of radionuclides in reactor coolant with half lives of >30 minutes.
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FUANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.2 REACTOR COOLANT SYSTEM SURVEILLANCE Applicability Applies to the reactor vessel, the reactor coolant syston and its components.
Objective To establish examinations whereby the reactor coolant system and component integrity is monitored.
Specification 4.2.1 The program for irradiation surveillance of the reactor vessel materials to monitor changes in the mechanical and impact properties shall be perforded as described in paragraph 4.4.5 of the FSAR.
Removal of specimens from carsules within the reactor shall be as scheduled in table 4.2-1.
4.2.2 An inservice inspection shall be made conforming as closely as design permits to the rules of the ASME Boiler and Pressure Vessel Code Section XI, Rules for Inservice Inspection of Nuclear Reactor Coolant Systems with revisions approved.as,of Jane 1973, tables IS-261, IS-251, and Section IS-240 of this Code will be used as a guide for determining the examination frequencies and the applicable specific areas to be examined. Thn inspection interval will be ten years. As part of the inservice inspection, hydrostatic tests will be performed as prescribed under Section IS-500 of this Code.
4.2.3 A preoperational examination will be made to include all the items that would normally be completed throughout the inspection interval.
This survey will establish initial system integrity and provide a baseline for future testing.
4.2.4 Each reactor coolant pump motor flywheel will be inspected volumetrically during the ten-year inspection interval. One hundred percent of the flywheel will be examined. All flywheels received a one hundred percent ultrasonic examination prior to installation on the motor.
Because the reactor coolant system was not designed to meet the requirements of Section XI of the ASME Boiler and Pressure Vessel Code, complete compliance is not feasible or practical. However, access for inservice inspection has been considered and design modifi-cations made where practical.
Therefore, where possible,Section II of this Code will be utilized in the conduct of this program. Table 4.2-2 itemizes those areas where l
complete compliance with the code is not possible be'cause of specific l
design and construction details.
4-10
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TECHNICAL SPECIFICATIONS Design Features 3.4 NEW AND SPENT FUEL STORAGE FACILITIES
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$.4.1 New Fuel Inspection and Temporary Storage Rack A.
New fuel shall be removed from the shipping containers, inspected and temporarily stored in the new fuel dry storage rack or stored in the pool. The dry storage rack is located on the operating floor and consists of two parallel modules containing ten spaces each on 21-1/8 inch centers. This spacing is sufficient to maintain Keff less than 0.9 when flooded with unborated water, based on a fuel enrichment of 3.5 weight percent U235 If the fuel assemblies have been stored in the dry storage rack, after inspection they may be moved to the new fuel elevator and lowered to the floor of the spent fuel storage pool, one at a time.(1) 8.
New fuel may also be stored in their shipping containers.
5.4.2 New and Spent Fuel Stotage Rachs and Failed Fuel Storage Container Rack New fuel while awaitino transfer to the Reactor Building and Irradiated or failed fuel prior ite shipment will be stored in the stain-less steel lined po, one spent fuel pool is sized to accommodate 579 fuel assemblies including 3 assemblies in failed fuel containers.
During refuelirg, the borated fuel pool water will have a minimum
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concentration of 1800 ppm.
The pool has the capability of storing new and spent fuel assemblies In fourter.n stainless steel rack modules and three failed fuel asserublies in a special rack module. All assemblics are on minimum 14.5 inch centers in both directions.
This spacing is sufficient to maintain K rr less than 0 95 when flooded with unborated water, based on a fuel e
enrichment of 3.5 weight percent.
5.4.3 New and Spent Fuel Temporary Storage The Reactor Building has one single row stainless steel stnrage rack in the deep portion of the refu ling canal. This rack is designed to hold six assemblics and one faiTed fuel detection can, all on 21-1/B Inch centers.
5.4.4 Spent Fuel Pool and Storage Rack Design The spent fuel pool and all storage racks are designed for the design base earthquake.
REFERENCE (1)
FSAR subsection 9.8 1
AmendmentNo./,
12 5-6 i
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2.4 jd!
Objective To prevent discharging acidic or basic liquids that would be detrimental to the terrestial environment within or near the receiving waters.
Specification Plant effluent pH shall be maintained within the limits of 6.5 to 8.5, except as allowed otherwise by the CRWQCB.
If the pH limit is exceeded, the discharge will be diverted to one of the two retention basins for holdup or the discharge will be terminated.
Monitoring Requirement Plant watar discharge pH shall be recorded continuously at the dis-charge structure. An alarm will be provided in the Control Room to warn the operator of exceeding the acceptable operating band betwr--
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6.5 and 8.5.
If the automatic diversica systes is inoper ble c:.ne pH monitor fails, the discharges will be manually channeled to t!.a retention basins. Samples will be obtained and analyzed to comp:y with these specificaticas prior to release to the discharge structure.
9 asis All plant effluent water will be transferred through the dilutica sump either directly to Clay Creek or temporarily to one of two 500,too gal.' retention basins before release to the creek. The restrict: ions require that discharged waste water not exceed the pH limits of 6.5 to 8.5, placing the water within the, National Technical Health :Jervice standards for drinking water for human consumption.
The combination of treatment, retention and dilut *nn of the pl::nt effluent water, coupled with the continuous monitoring program, will assure that effluent quality conforms with CRWQCB standards an(:. will permit safe disposal of the effluent to the public domain.
2.5 Other Chemicals Which Affect Water Quality Obj ective To assure that ef fluent water is sufficiently pure that its receiving waters will support aquatic life.
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Specification A.
The discharge shall not cause the concentration of dissolved oxygen in the receiving waters to be less than 5.0 mg/1.
B.
The ef fluent water shall not contain dissolved boron in excess of 1.2 mg/L or 48 lbs per day and 1.0 mg/1 or 40 lbs/ day when averaged over 30 days.
C.
The ef fluent water shall not contain dissolved zine in excess of 0.4 ag/L or 16 lbs per day and 0.3 mg/L or 12 lbs/ day when l
averaged over 30 days.
Monitoring Requirement Grab samples of the plant effluent water for oxygen analysis shall be obtained 100 yards downstream of the plant discharge and from Hadsel-ville Creek at points 100 yards upstream and 100 yards downstream of the confluence'with Clay Creek and analyzed weekly. These samples will give an indication of the quality of the efflucat water from the plant and be representative of the overall plant cperations.
Samples of the effluent water for boron and zine analysis shall be collected and analyzed on a monthly 24-hour composite schedule. The samples will be obtained from the outlet of the discharge structure.
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Basis All limitations in this specification were established by the CRWQCB.
The Aquatic Life Advisory Committee
- recommends that the dissolved oxygen content of warm-water fish habitats be not less than 5 mg per liter during at least 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> of any 24-hour pskiod. It may be less than 5 mg per liter f or a period not to exceed 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> within any 24-hour period, but at no time.should the dissolved oxygen content be less than 3 mg per liter.
The above analyses indicate that there is a reasonable assurance that a minimum of 5.0 mg per liter dissolved oxygen in the plant effluent will not adversely affect fish life in the receiving waters.
Dissolv'ed oxygen of the effluent waters should be near saturation because of the aeration within the cooling towers.
The minute quantities of boron and zine are received from the'Folsom South Canal as makeup water and concentrate in the cooling towers.
Dilution before discharge may be required to reduce the levels below these limits.
l These elements may be present in the plant, but are mainly derived from the concentrating mechanisms of the cooling towers and, in general, are l
not of plant origin.
Anon., Aquatic Life Water Quality Criteria, First Progress Report, Ohio River ys11ey Water Sanitation Commission, Aquatic Life Advisory Committee, Sewage &
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Industrial Wastes 27, 321 (1955).
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- Amendment No. 12 l
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C.
Sampling and analysis of liquid radioactive waste shall be per-formed in accordance with Table 2.6-1.
Prior to taking samplus from a monitoring tank, at least two tank volumes shall be recirculated or the agitator shall be operated sufficiently to achieve complete mixing.
D.
The liquid radioactive wastes shall be continuously monitored and recorded during release. Whenever these monitors are inoperable for a period not to exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, two independent samples of each tank to be discharged shall be analyzed and two plant personnel shall independently check valving prior to the discharge.
If these monitors are inoperable for a period exceeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, no liquid waste tank shall be released and any release in prograss shall be terminated.
4 E.
The flow rate of liquid radioactive waste after dilution shall be measured and recorded during release. The flow of undiluted liquid radioactive waste shall be estsblished using installed instrumentation. That flow rate shall be entered in the plant records for the liquid waste release.
F.
All liquid radiation monitors shall be calibrated at least quarterly by means of a radioactive source which has been calibrated to a National Bureau of Standards source. Each
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monitor shall also have a functional test monthly and an instrument check prior to making a release.
- Bases The release of radioactive materials in liquid waste to unrestricted areas shall not exceed the concentration Itzits specified in 10 CFR Part 20 and should be as low as practicable in accordance with the requirements of 10 CFR Part 50.36a. These specifications provide reasonable assurance that the resulting annual exposure to the total body or any organ of an individual in an unrestricted area will not exceed 5 arem. At the same time, these specifications permit the flexibility of operation, compatible with considerations of health and safety, to assure that the public is provided a dependable source of power under unusual operating conditions which may temporarily result in releases higher than the design objective Irvels but still within the concentration limits specified in 10 CFR Part 20.
It is expected that by using this operational flexibility under unusual operation conditions, and exerting every effort to keep levels of radioactive material in liquid wastes as low as practicable, the ann'ual releases will not exceed a small fraction of the concentration limits specified in 10 CFR Part 20.
The design objectives have been developed based on operating experience taking into account a combination of variables including defective fuel, primary system leakage, primary to secondary system leakage and the performance of the various vaste treatment systems, and are consistent with Appendix 1 to 10 CFR Part 50. Amendment No. J2
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1 Specification 2.6.1.A requires the licensee to limit the concentration of radioactive materials in liquid wastes from the site to levels specified in 10 CFR Part 20, Appendix B. Table II, Column 2, for unrestricted areas.
This specification provides assurance that no member of the general public will be exposed to liquid containing radioactive materials in excess of limits considered permissible under the Commission's Rules and Regulations using the guidelines given in Regulatory Guide 1.21.
Specifications 2.6.1.B and 2.6.1.C establish the upper limits for the release of radioactive materials in liquid affluents. The intent.of these Specifications is to permit the licensee the flexibility of operation to assure that the public is provided a dependable source of power under unusual operating conditions which may temporarily result in releases higher than the levels normally achievable when the plant and the liquid waste treatment systems are functioning as designed.
Re-leases of up to thest' limits will result in concentrations of radioactive material in liquid wastes at small percentages of the limits specified in 10 CFR Part 20.
Specifications 2.6.1.D and 2.6.1.E require that suitable equipment to con-trol and monitor the releases of radioactive materials in liquid wastes
- c;erating during any period these releases ar2 taking place consistent
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with.the requirements of 10 CFR Part 50, Appendix A, Desiga Criterion 64.
Specification 2.6.1.F requires that the licensee maintain and operate
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the equipment installed in the liquid waste systems to reduce the release I
of radioactive materials in liquid effluents to as low as practicable consistent with the requirements of 10 CFR Part 50.36a. Normal use and maintenance of installed equipment in the liquid waste system provides reasonable assurance that the quantity released will not exceed the i
design objective. In order to keep releases of radioactive materials
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as low as practicable, the specification requires operation of equipment whenever it appears that the projected cumulative discharge rate will exceed one-fourth of this design objective annual quantity during acy calendar quarter.
Specification 2.6.1.G limits the amount of radioactivity that may be inadvertently released to the environment to an amount that will not exceed the Technical Specification limit.
.In addition to limiting conditions for operation listed under Specification 2.6.1.B and 2.6.1.C, the reporting requirements of Specification 2.6.1.H delineate that the licensee shall identify the cause whenever the release rate of radioactive materials in liquid wastes exceeds one-half the design objective annual quantity during any calendar quarter and describe the proposed program,of action to reduce such release rate to design objective levels on a timely basis. This report must be filed within 30 days following the calendar quarter in which the release occurred..
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