ML19317G800
| ML19317G800 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 03/05/1976 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19317G794 | List: |
| References | |
| NUDOCS 8004010629 | |
| Download: ML19317G800 (14) | |
Text
{{#Wiki_filter:* UNITED STATES ftUCLEAR REGULATORY COMMISSION W AS HtN C TO N, D. C. 2055 5 9 SACRAMENTO MUNICIPAL UTILITY DISTRICT DOCKET NO. 50-312 RANCHO SECO NUCLEAR GENERATING STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 3 License No. DPR-54 1. The Nuclear Regulatory Commission (the Commission) has found that: A. The applications for amendment by Sacramento Municipal Utility District (the licensee) dated March 12, April 7, and May 30, 1975, comply 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 Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such setivities 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 sf the public; and E. An environmentalistatement or negative declaration need not be prepared in connection with the issuance of this amendment. 2. Accordingly, the license is amended by a change to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility License No. DPR-54 is hereby amended to read as follows: 8004010 f
. "(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specificat!.ons." 3. This license amendment is effective as cf the date of its issua'nce. FOR THE FJCLEAR REGULATORY C0bHISSION (7 (g'-{u./Vlll% Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors i
Attachment:
Changes to the Technical Specifications Date of Issuance: M4lt. 5 3 73 f
. -g ATTACHMENT TO LICENSE AMENDMENT NO. 3 FACILITY OPERATING LICENSE NO. DPR-54 DOCKET NO. 50-312 Revise Appendix A as follows: Remove Pages Insert Pages Figure 2.3-2 Figure 2.3-2 3-6 3-6 3-32 3-32 3-33 3-33 3-33a 3-33a 3-33b 3-33b 3-33c Figure 3.5.2-1 Figure 3.5.2-2 3-51
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!- } [ I f f i i 1 -60 -40 -20 0 20 40 60 . Power Imbalance, % FIGURE 2.3 2 RANCHO SECO UNIT 1 PROTECTIVE SYSTEM MAXIMUM TECHNICAL SPECIFICATIONS ALLOWABLE SET POINTS h V5) 0Y$ SMUD FSAR - 615 SACRAMENTO MUNICIPAL UTILITY DISTRICT I ~ Anendment No. 3 k-T n A
'g RANCil0 SECO UNIT 1 TEONICAL SPECIFICATIONS Limiting Conditions for Operation 3 1.3 MINUMUM CONDITIONS FOR CRITICALITY _ Specifications 3.1.3.1 The reactor coolant temperature shall be above 525 F except for portions of low power physics testing when the requirements of Specification 3.1.8 shall apply. 3.1.3.2 Reactor coolant temperature shall be above DTT + 10 F. 3.1.3.3 Uhen the reactor coolant temperature is below the minumum tempera-ture specified in 3.1.3.1 above, except for portions of low power physics testing when the requirements of Specification 3.1.8 shall apply, the reactor shall be suberitical by an amount equal to or greater than the calculated reactivity insertion due to depressurization. 3.1.3.4 The reactor shall be maintained suberitical by at 1 cast 1 percent ak/k until a steam bubble is formed and an indicated water level between 10 and 316 inches is established in the pressurizer. 3.1.3.5 Except for physics tests and as limited by 3.5.2.1 and 3.5.2.5, safety rod groups shall be fully withdrawn prior to any other reduction in shutdown margin by deboration or regulating rod withdrawal during the approach to criticality. Following safety rod withdrawal, the regulating rods shall be positioned within their position limits as defined by specification 3.5.2.5 prior to deboration. Bases At the beginning of life of the initial fuel cycle, the moderator temperature coefficient is expected to be slightly positive at operating temperatures with , the operating configuration of. control rods.~(1) Calculations show that above S 525 F the positive moderator coefficient is acceptable. Since the moderator temperature coefficient at lower temperatures.will be less negative or more positive than at operating temperature,(2) startup and opera ' tion of the reactor when reactor coolant temperature is less tan 525 F is pro-hibited except where necessary for low power physics tests. The potential reactivity insertica due to the moderator pressure coeffi-cient(2) that could result from depressurizing the coolant from 2185 psia to saturation pressure of 885 psia is approximately 0.1 percent ak/k. During physics tests, special operating precautions will be taken. In addi-tion, the strong negative Doppler coefficient (1) and the small integrated Ak/k would limit the magnitude of a power excursion resulting from a reduc-tion of moderator density. l Amendment No. 3 3-6 n
01 RANCHO SECO UNIT 1 TECICTICAL SPECIFICATIONS Limiting Conditions for Operation I. F. If a control rod in the regulating or axial power shaping groups is declared inoperable per Specification 4.7.1.2, operation above 60% of rated power may continue provided the rods in the group are positioned such that the rod that was declared inoperable is maintained within allowable group average position limits of Specification 4.7.1.2 and the with-drawal limits of Specification 3.5.2.5.c. 4 3.5.2.3 The worth of a single inserted control rod shall not exceed 0.65 ^ percent Ak/k at rated power or 1.0 percent Ak/k at hot zero power-except for phys'ics testing when the requirement of Specification 3.1.8 shall apply. 3.5.2.4 Quadrant tilt: A. Whenever the quadrant power tilt e::ceeds 4 percent, except for physics tests, the quadrant tilt shall be reduced to less than 4 percent within two hours or the following actions shall be i taken: (1) If four reactor coolant pu=ps are in operation, the allowable thermal power shall be reduced by 2 percent + of maximum allowable power for each I percent tilt in excess of 4 percent. Maximum allowable power is defined in Technical Specifications Section 1.1. The allowable thermal power is defined by Figure 3.5.2-1 ( where the power level cutoff may apply during transient zenon operation. (2). If less than four reactor coolant pumps are in operation. -l the allowable thermal power shall be reduced by 2 percent of marimum allowable power for each 1 percent tilt below the power allowable for the reactor coolant pump combin-ation. (3) Except as provided in 3.5.2.4.b. the reactor shall be brought to the hot shutdown condition within four hours if the quadrant tilt is not reduced to less than 4 per-cent after 24 hours. (4) The power range high flux set point shall be reduced 2 percent of the maximum allowable flux for the RC pump combination for each 1 percent. tilt in excess of 4 per-cent. S. If the quaorant tilt exceeds 4 percent and there is simultaneous indication of a misaligned control rod per Specification 3 5.2.2, reactor operation may continue, provided power is reduced to 60 percent of the thermal power allowable for the reactor coolant pump con 61 nation. Amendment No. 3 3-32 g
?" RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation C. Except for physics tests, if quadrant tilt exceeds 9 percent, f' the reactor shall be brought to the hot shutdown condition within four hours. D. Whenever the reactor is brought te hot shutdown pursuant to 3.5.2.4a(3) or 3.5.2.4.c above, subsequent reactor operation is permitted for the purpose of measurement, testing and corree-tive action provided the thermal power and the power range high flux setpoint alloweble for the reactor coolant pump combination are restricted by a reduction of 2 percent of maximum allowable power for each I percent tilt. E. Quadrant power tilt shall be monitored on a minimum frequency of once every two hours during power operation above 15 percent of rated power. 3.5.2.5 Control Rod Positions A. Technical Specification 3.1.3.5 (safety rod withdrawal) does not prohibit the exercising of individual safety rods as required by table 4.1-2 or apply to inoperable safety rod limits in Technical Specification 3.5.2.2. B. Operating rod group overlap shall be 25 percent i 5 percent between two sequential groups, except for physics tests. ( C. Except for physics test or exercising control rods, the control rod withdrawal limits are specified on figure 3.5.2-1. If the control rod position limits are exceeded, corrective measures shall be taken immediately to achieve an acceptable control rod position. Acceptable control rod positions shall then be attained within two hours. g. D. Except for physics tests, power shall not be increased above the power level cutoff of figure 3.5.2-1 unless one l-of the following conditions is satisfied: (1) Xenon reactivity is within 10 percent of the equilibrium value for operation at the maximum power level (94.9% or 100% as applicable) and asymptotically approaching stability. This condition must be satisfied for a xenon free startup. or (2) The reactor power shall be held for a minimum of two hours in the soluble boron control mode within a band extending from 5%Fp below power Level Cutoff up to power Level Cutoff of figure 3.5.2-1. I 3-33 Amendment No. 3 i
,3 ( IUL';CHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation !( 3.5.2.6 Reactor power imbalance shall be monitored o'n a frequency not to exceed two hours during power operation above 40 percent rated power. Except for physics tests, imbalance shall be maintained within the i envelope defined by Figure 3.5.2-2. If the imbalance is not within the envelope defined by figure 3.5.2-2, corrective measures shall be taken to achieve an accep. table imbalance.. If an acceptable imbalance is not achieved within two hours, reactor power shall be reduced until imbalance limits are met.- 3.5.2.7 The control rod drive patch panels shall be locked at all times with limited access to be authorized by the superintendent or his designated representative. Bases The power-imbalance envelope defined in Figure 3.5.2-2 is based on LOCA analyses which have defined the maximum linear heat rate (see figure 3.5.2-3) such that the maximum clad temperature will not exceed the Im trim Acceptance Criteria. Operation outside of the power imbalance envelope alone does not constitute a situation that would cause the Interim Acceptance Criteria to be exceeded should c LOCA occur. The power imbalance envelope represents the boundary of operation limited by the Interim Acceptance Criteria only if the control reds are at the position limits as defined by figure 3.5.2-1 !( and if a 4 percent quadrant power tilt exists. Additional conservatism is introduced by application of: A. Nuclear uncertainty factors. B. Thermal calibration uncertainty. C. Fuel densification effects. D. Hot rod manufacturing tolerance factors. i The 25 percent overlap between successive control rod groups is allowed since l the worth of a rod in lower at the upper and lower urt of the stroke. Control rods 'are arranged in groups defined as follows:
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Group Function 1 Safety 2-Safety 3 Safety 4 Safety 5 Regulating 6 Regulating 7 Regulating 4 8 APSR (axial power shaping rods) 3-33a Amendment No. 3 1 I i
em RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 'I Control rod groups are withdrawn in sequence beginning with group 1. Group 5 is overlapped 25 percent with groups 6 and 7, which operate in parallel. The normal position at power is for groups 6 and 7 to be partially inserted. The minimum available red worth provides for achieving hot shutdown by reactor trip at any time assuming the highest worth control rod remains in the full out position. (1) Inserted rod groups during power operation will not contain single rod worths 4 greater than 0.65 percent ak/k. This value has been shown to be safe by the j safety analysis of the hypothetical rod ejection accident. (2) A single inserted control rod worth of 1.0 percent ak/k at beginning of life, hot, zero power would result in a lower peak thermal power and therefore less severe environnental consequences than 0.65 percent ak/k ejected rod worth at power. The quadrant power tilt limits set forth in Specification 3.5.2.4 have been established within the thermal analysis design base using the definition of quadrant power tilt given in Technical Specifications, Section 1.6. These limits in conjunctio,n with the control rod position limits in Specification 3.5.2.5c ensure that design peak heat rate criteria are noc exceeded during normal operation when including the effects of potential fuel densification. The quadrant tilt and axial imbalance monitoring in Specifications 3.5.2.4 and 3.5.2.6, respectively, normally will be performed in the process computer. The two-hour frequency for monitoring these quantities will provide adequate surveil-lance when the computer is out of service. Allowance is provided for withdrawal limits and reactor power imbalance limits to be exceeded for a period of two hours without specification violation. Accept-able rod positions and imbalance must be achieved within the two-hour time period or appropriate action such as a reduction of power taken. Operating restrictions are included in Technical Specifications 3.5.2.5d (1) and 3.5.2.5d (2) to prevent excessive power peaking by transient xenon. The xenon reactivity must either be beyond the "undershoot" region and asymptotically approaching its equilibrium at rated power or the reactor must be operated for a minimum of two hours within a band extenling from 5% FP below power level cutoff up to power level cutoff in the soluble poison control mode so that the transient peak is burned out at a lower power level. During physics testing, additional safety margins are provided by administrative 1y setting special reactor protection system limitations. During the power ascension testing program, the following high flux trip setting will be set prior to in-creasing to the next plateau. Amendment No. 3 l '1 -s n,5.-, ~g-- .--v
m i RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation k Test Plateau Level % Overpower Trip % 0 <5 15 50 40 50 75 95 90 100 100 105.5 ,. ( et 1 i l l i REFERENCES (1) FSAR, paragraph 3.2.2.'1.2 (2) FSAR, paragraph 14.2.2.4 l Amendment No. 3 3-33c i (. ~ l i n 's, 9 6% ~ Q =
, m. I I I I i l l l l ( 100 (180.s,102) 9, (195. 6,16z) 90 P01tER LEVEL CUT 0FF 92 % i(2co,92) (179.3,92) i 172,82) 80 70 60 Region ~ 5 50 s5 (122.3,43) g W a i 30 Pe rm, ss, bl e g i i (, Operating 20 Region (so,15) 10 0 I I I I I I I I 0 20 60 80 100 120 1% 160 180' 20 0 Rod Index, 7. Wi thdrawn 0 25 50 75 100 l I I l 1 0 25 50 75 10 0 Group 6 & 7 I l I l l Group 5 1. Rod index is the percentage sum of the withdrawal of control rod groups 5,6 & 7 2. The restrictions on rod position are in effect after 100 EFPD R0D POSITION LIMITS
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1 g 60 J M o 50 '8"'f + ,, is.2,v3 g 40 E 30 ( 20 10 0 -60 -40 -20 0 +20 +40 +60
- 1. The limi ts are in ef fect af ter 100 EFPD.
OPER ATION AL POWER IMBAL AN CE EN V ELOP E Fi gu re 3. 5. 2-2 t/ Amendment No. 3 (. .}}