ML20247A542
| ML20247A542 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 08/31/1989 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247A547 | List: |
| References | |
| NUDOCS 8909120141 | |
| Download: ML20247A542 (13) | |
Text
{{#Wiki_filter:- - _ _ _ _ _ _ .i- ,j#"'[*4,T 'D UNITED STATES j"- NUCLEAR REGULATORY COMMISSION g' y = . WASHINGTON, D. C. 20555 %y. p SYSTEMS ENERGY RESOURCES INC., et al. DOCKET NO. 50-416 GRAND GULF NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE' Amendment No. 62 License No. NPF-29 '1. ' The Nuclear _ Regulatory Comission (the Commission) has found that. A._ The application for amendment by System Energy Resources, Inc., (the licensee),- dated December 18, 1988, as. revised February 24, 1989,. complies with the standards and requirements of the Atomic Energy Act of 1954, as amended-(the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility. will operate in conformity with the application, the . provisions of the Act, and the rules and regulations of the 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 activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. h P
.s i s V -2'. - 2. ' Accordingly,. the' license is anended by changes to the Technical Specifications, as indicated in the. attachment to this license amendment; and paragraph 2.C.(7) of Facility Operating License. No. NPF-29 is hereby amended.to read as follows: (2)' Technical Specifications-The Tech'nical Specifications contained'in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through knendment No. 62, are hereby. incorporated into this license. System Energy Resources, Inc. shall operate the facility .in accordance with the Technical Specifications and the Environmental Protection Plan. 3. .This license amendmant is effective as of its date of issuance. FOR THE HUCLEAR REGULATORY COMMISSION Original. Signed By: Elinor G. Adensam, Director Project Directorate 11-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation Attachnent: Changes to the Technical . Specifications Date of Issuance: ' August 31, 1989 e U M r J' i c i /~ ( DF C - : LA: 2p:t RPR:PM:P
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9 z. ATTACHMENT.TO. LICENSE. AMENDMENT.NO. 62 FACILITYOPERATING. LICENSE.NO..NPF-{9 DOCKET N0. 50 416 ' Replace the following pages of the Appendix "A" Technical Specifications with the~ attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. Remove Insert l l v v 3/4 3-111 3/4 3-111 3/4 3-112 3/4 4-1 3/4 4-1 3/4 4-la 3/4 4-la 3/4 4-Ib. 3/4 4-lb 3/4 4-Ic 3/4 4-Ic B3/4 3-7 83/4 3-7 B3/4 4-1 B3/4 4-1 B3/4 4-la B3/4 4-la B3/4 4-lb = _ _ _ _ _ _ _ _ _ _ _
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'l .INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION. PAGE L3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION................. 3/4-3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION......................... 3/4 3-9 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION..... 3/4 3-27. 3/4.3.4 RECIRCULATION PUMP TRIP ACTUATION' INSTRUMENTATION ATWS Recirculation Pump Trip System Instrumentation......... 3/4 3-37 End of-Cyc1e' Recirculation Pump Trip System Instrumentation............................................. 3/4 3-41 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION........................... 3/4 3-47 3/4.3.6 CONTROL R0D BLOCK INSTRUMENTATION........................... 3/4 3-52 3/4.3.7 MONITORING INSTRUMENTATION-Radiation Monitoring Instrumentation........................ -3/4 3-58 Seismic Monitoring. Instrumentation;......................... 3/4 3-63 Meteorological Monitoring Instrumentation................... 3/4 3-66 Remote Shutdown System Instrumentation and Controls......... 3/4 3-69 Accident Monitoring Instrumentation......................... 3/4 3-73 Source Range Monitors....................................... 3/4 3-77 l Traversing In-Core Probe System............................. 3/4 3-78 Chlorine Detection System................................... 3/4 3-79 Fire Detection Instrumentation.............................. 3/4 3-80 L Loose-Part Detection System................................. 3/4 3-90 Radioactive Liquid Effluent Monitoring Instrumentation...... 3/4 3-91 i Radioactive Gaseous Effluent Monitoring Instrumentation..... 3/4 3-96 3/4.3.8 PLANT SYSTEMS ACTUATION INSTRUMENTATION..................... 3/4 3-105 3/4.3.9 -TUR8INE OVERSPEED PROTECTION SYSTEM.......................... 3/4 3-110 1 GRAND GULF-UNIT 1 v Amendment No. 62
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l:.. i ( Pages 3/4 3-111 and 3/4 3-112 Intentionally Deleted -GRAND GULF-UNIT 1 3/4 3-111 Amendment No. 62 ) l
] 3/4.4' REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM RECIRCULATION LOOPS LIMITING CONDITION FOR OPERATION 3.4.1.1 The~ reactor coolant recirculation system shall be in operation with l .either: a.- Two recirculation loops operating with limits and setpoints per Specifications 2.1.2, 2.2.1, 3.2.1, and 3.3.6, or b. A single recirculation loop operating with: 1. A volumetric loop flow rate less than 44,600 gpm, and 2. The loop recirculation flow control in the manual mode, and 3. Limits and setpoints per Specifications 2.1.2, 2.2.1, 3.2.1, and 3.3.6. Operation is not permissible in Regions A, B or C as specified in Figure 3.4.1.1-1 except that operation in Region C is permissible during control rod i withdrawals for startup. APPLICABILITY: ' OPERATIONAL CONDITIONS 1* and 2*. ACTION: a. With no reactor coolant system recirculation loops in operation and -the reactor mode switch in the run position, immediately place the reactor mode switch in the shutdown position. b. With operation in Region A as specified in Figure 3.4.1.1-1, immediately place the reactor mode switch in the shutdown position. c. With operation in regions B or C as specified in Figure 3.4.1.1-1, observe the indicated APRM, neutron flux noise level. With a sustained APRM neutron flux noise level grsater than 10% peak-to peak of RATED THERMAL POWER, immediately place the reactor mode switch in the shutdown positicn. d. With operation in Region B as specified in Figure 3.4.1.1-1, immediately initiate action to either reduce THERMAL POWER by inserting control rods or increase core flow if one or more recirculation pumps-are on fast speed by opening the flow control valve to within Region D of Figure 3.4.1.1-1 within 2 hours. e. With operation in Region C as specified in Figure 3.4.1.1-1, unless operation in this region is for control rod withdrawals during startup, immediately initiate action to either reduce THERMAL POWER or increase core flow to within Region D of Figure 3.4.1.1-1 within 2 hours, f. During single loop operation, with the volumetric loop flow rate greater than the above limit, immediately initiate corrective action to reduce flow to within the above limit within 30 minutes. ^5ee Special Test Exception 3.10.4. GRAND GULF-UNIT 1 3/4 4-1 Amendment No. 62 j
[( p ..s. -REACTOR COOLANT SYSTEM-l LIMITING CONDITION FOR OPERATION (Continued) ~ h g. During single loop operation, with the loop flow control not in the manual mode, place it in the manual mode within 15 minutes. h. During single loop operation, with temperature. differences exceeding the limits of SURVEILLANCE REQUIREMENT 4.4.1.1.5, suspend the THERMAL POWER or recirculation loop flow increase. ~ l i. With a change in reactor operating conditions, from two recircula-tion ~1 oops operating to single loop operation, or restoration of two loop operation, the limits and setpoints of Specifications 2.1.2, 2.2.1, 3.2.1, and 3.3.6 shall be implemented within 8 hours or . declare the associated equipment inoperable (or the limits to be "not satisfied"), and take the ACTIONS required by the referenced specifications. SURVEILLANCE REQUIREMENTS 4.4.1.1.1 At least once per 24 hours, the reactor coolant recirculation system shall be verified to be.in operation and not in Regions A, B or C as specified Lin Figure 3.4.1.1-1 except that operatien in Region C is permissible during control rod withdrawals for startup. 4.4.1.1.2 Each reactor coolant. system recirculation loop flow control valve in an operating loop shall be demonstrated OPERABLE at least once per 18 months by: Verifying that the control valve fails "as is" on loss of hydraulic a. pressure at the hydraulic unit, and b. Verifying that the average rate of control valve movement is: 1. Less than or equal to 11% of stroke per second opening, and l' 2. Less than or equal to 11% of stroke per second closing. 4.4.1.1.3 During single loop operation, verify that the loop recirculation flow control in the operating loop is in the manual mode at least once per 8 hours. 4.4.1.1.4 During single loop operation, verify that the volumetric loop flow rate of the loop in operation is within the limit at least once per 24 hours. l l^ 1 GRAND GULF-UNIT 1 3/4 4-la Amendment No. 62 _____x
qq REACTOR COOLANT SYSTEM LIMITING-CONDITION FOR OPERATION (Continued) 4.4.1.1.5 During single loop operation, and with both THERMAL POWER less than 36% of RATED THERMAL POWER and the operating recirculation pump not on high speed, verify that the following differential temperature requirements are met within 15 minutes prior to beginning either. a THERMAL F0WER increase or a recirculation loop flow increase and within every hour during the THERMAL POWER or recirculation loop flow ^ increase: Less than 100 F, between the reactor vessel steam space coolant and a. the bottom head drain line coolant, and b. Less than 50 F, between the coolant of the loop not in operation and the coolant in the reactor vessel, and-Less than 50 F, between the coolant in the operating loop and the c. coolant in the loop not in operation. The differential temperature requirements 4.4.1.1.5.b and c.do not apply when the loop not in operation is isolated from the reactor pressure vessel. 4.4.1.1.6 The limits and setpoints of Specifications 2.2.1, 3.2.1, and 3.3.6 shall be verified to be within the appropriate limits within 8 hours of an operational change to either one or two loops operating. GRAND GULF-UNIT 1 3/4 4-lb Amendment No. 62
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INSTRUMENTATION BASES 3/4.3.9 TURBINE OVERSPEED PROTECTION This specification is provided to ensure that the turbine overspeed protection instrumentation and the turbine speed control valves are OPERABLE and will protect the turbine from excessive overspeed. Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage safety-related components, equipment or structures. 3/4.3.10 DELETED GRAND GULF-UNIT I B 3/4 3-7 Amendment No. 62
y l l.- 3/4.4 REACTOR COOLANT SYSTEM BASES ~ _ _. _ _. 3/4.4.1 RECIR[ULATIONSYSTEM' ~Operaticn with one reactor' core coolant recirculation loop inoperable has been evalmted and found to remain within design limits and safety margins pro-vided certain limits and setpoints are modified. The 'G3NS Single Loop Opera-tion Analysis" icentified the fuel cladding integrity Safety Limit, MAPLHGR limit and A M M setpoint modifications necessary to maintain the same margin of l. safety for vingle loop operat4n as is available daring two loop operation. Additionally, loop ficw limitations are establi@ed to ensure vessel internal vibration remains within limits. A flow control code restriction is also incorporated te reduce velve wear as a result of aetomatic flow control attempts and to ensure valve swings into the cavitation region do not occur. An inoperable jet pump.is net, in itself, a sufficient reason to declare a rec %rculation loop inoperable, but it does, in case of a design-basis-accident, increase the blowdown area and reduce the capability of reflooding the core; thus, the requirement for shutdown of the facility with a jet pump inoperable. Jet pemp failure can be detected by monitoring jet pump per-tormance on a prescribed schedule'for significant degradation. During two loop operation, recirculation loop flow mismatch limits are in compliance with ECCS LOCA analysis design criteria. The limits will ensure an adequate core flow coastdown.from e'ther recirculatim loop following a LOCA. In cases where the mismatch linits cannot be maintained, continued operation is per-mitted with one loop in operation. The power / flow operating map'is divided into four (4) regions. Regicns A and.B are restricted from operations. They include the operating area above the 80% rod-line and below 40% core flow. Region C includes the operating area'above the 80% rod-line and between 40% and 45% core flow. Operation in Region C is allowed only far control rod withdrawals during startup for required fuel preconditioning. Region D consists of the rest of the operating map. No core thermal-hydraulic stability related restrictions are applied to Region D since the potential onset of core thermal-hydraulic instabilities is not predicted within Region L. The definition of Regions A, B and C is based on BWR stability operational data and required operator actions. Although a large margin to onset of insta-bility was observed in Regions A, B and C during GGNS stability tests for typical operating configuration, a conservative approach is adopted in the specification. With no reactor coolant system recirculation loops in operation, and the reactor mode switch in the Run position, an immediate reactor shutdown is required. Reactor shutdown is not required when recirculation pump motors are de-energized during recirculation pump speed transfers. Upon entry to Region A an immediate reactor shutdown is required. Upon entry to Region B or Region C, unless operation in Region C is for control rod withdrawals during startup, i either a reduction of THERMAL POWER to below the 80% rod-line by control rod insertion or an inrease in core flow to exit the region by opening the recirculation loop FCV is required. Per the specification, the APRM neutron flux noise level should be observed while in Regions B and C. In the unlikely event in which a sustained GRAND GULF-UNIT 1 B 3/4 4-1 Amendment No. 62
4 ~ L REACTOR COOLANT SYSTEM BASES L 3/4.4.1 RECIRCULATION SYSTEM (Continued) l APRM neutron flux noise level exceeding 10% peak-to peak of RATED THERMAL POWER is observed, an immediate reactor shutdown is required. l The APRM neutron flux noise level of 10% peak-to peak of RATED THERMAL I POWER is established to. ensure early detection of core thermal-hydraulic instabilities. APRM neutron flux noise levels in the range of 2% to 6% peak-to peak of RATED THERMAL POWER were observed for the Grand Gulf Reactor during its first three operating cycles and at different power / flow operating conditions. This represents the typical APRM neutron flux noise level for stable operations of the Grand Gulf Reactor. The 10% peak-to peak of RATED THERMAL POWER noise level provides adequate margin to thermal limits in the unlikely event of uncontrolled limit cycle oscillations while in Regions B and C, including the even less likely event of regional oscillations. The required operator action of an immediate reactor shutdown upon entry to Region A and upon detection of sustained APRM neutron flux noise level greater than the 10% peak-to peak of RATED THERMAL POWER assures that an adequate margin to thermal limits will be maintained at all times. In order to prevent undue stress on the vessel nozzles and bottom head region, the recirculation loop temperatures shall be within 50 F of each other prior to startup of an_ idle loop. The loop temperature must also be within 50 F of the reactor pressure vessel coolant temperature to prevent thermal shock to the recirculation pump and recirculation nozzles. Since the coolant in the bottom of~the vessel.is at a lower temperature than the coolant in the upper regions of the core, undue stress on the vessel would result if the temperature difference was greater than 100 F. During single loop operation, the condi-tion may exist in which the coolant in the bottom head of the vessel is not circulating. These differential temperature criteria are also to be met prior to power or flow increases from this condition. The recirculation flow control valves provide regulation of irdividual recirculation loop drive flows; which, in turn, will vary the flow rate of coolant through the reactor core over a range consistent with the rod pattern and recirculation pump speed. The recirculation flow control system consists of the electronic and hydraulic components necessary for the positioning of ' tne two hydraulically actuated flow control valves. Solid state control logic will generate a flow control valve " motion inhibit" signal in response to any one of several hydraulic power unit or analog control circuit failure signals. The " motion inhibit" signal causes hydraulic power unit shutdown and hydraulic isolation such that the flow control valve fails "as is." This design feature insures that the flow control valves do not respond to potentially erroneous control signals. GRAND GULF-UNIT 1 B 3/4 4-la Amerdment No. 62
4 - 4 i REACTOR COOLANT SYSTEM BASES 3/4.4.1 RECIRCULATION SYSTEM (Continued) Electronic limiters exist in the position control loop of each flow control valve to limit the flow control valve stroking rate to 10 1% per second in the opening and closing directions on a control signal failure. The analysis of the recirculation flow control failures on increasing and decreasing flow are presented in Sections 15.3 and 15.4 of the FSAR respectively. The required surveillance interval is adequate to ensure that the flow control valves remain OPERABLE and not so frequent as to cause excessive wear on the system components. {' \\ i GRAND GULF-UNIT 1 B 3/4 4-lb Amendment No. 62 l l}}