ML20155J360
| ML20155J360 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 10/12/1988 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20155J366 | List: |
| References | |
| NUDOCS 8810260042 | |
| Download: ML20155J360 (7) | |
Text
_ __________ _ _
i
'o UNITED STATES g'
[
g NUCLEAR REGULATORY COMMISSION y
WASHING TON, D. C. 20666
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GULF STATES llT_ILITIES COMPANY DOCKET NO. 50-458 RIVER BEND STATION, UNIT 1 AMENCMENT TO FACRITY OPERATING LICENSE l
Amendment No. 29 License No. NPF-47 1.
The Nuclear Regulatory Comission (the Connission) has found that:
A.
The application for arendment by Gulf States Utilities Company l
(the licensee) dated August 5, 1988, complies with the standards l
and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Connission; C.
There is reasonable assurance:
(i) that the activities authorized by this arendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be i
conducted in compliance with the Comission's regulations; 1
D.
The issuance of this license amendrent will not be inimical to the comen defense and security or to tno healtn and safety of the public; and E.
The issuance of this amendrent is in accordance with 10 CFR Part 51 of the Connission's regulations and all applicable requirements have been satirfied.
8G10260043.GAJ012 PDR ADOth Ob'000458 P
2 7.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph ?.C.(2) of Facility Operating License No. NPF-47 is hereby amended to read as follows:
(2) Technical Specifications and Environmental _ Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 29 and the Environmental Protection Plan contained in Appendix B, are hereby incorpoYated in the license.
GSU shall operate the facility in accordence with the Technical Specifications and the Environmental Protection Plan.
3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION d
tG. M c.
' Jose A. Calvo, Director Project Cirectorate - IV Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Chansas to the Technical Specifications Date of Issuance: October 12, 1988 i
ATTACHMENT TO LICENSE AMENDMENT NO. 29 FACILITY OPERATING, LICENSE N0_._NPF-47 DOCKET NO. 50-458 7
Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by An.endment number and contain a vertical line indicating the area of change. Overleaf page provided to raintain docurent completeness.
REMOVE PAGES INSERT PAGES 1-?
1-2 3/4 3-4 3/4 3-4 i
.I 4
e i
l 4
1.0 DEFINITIONS The following terms are defined so that uniform interpretation of these specifications may be achieved. The defined terms appear in capitalized type and shall be applicable throughout these Technical Specifications.
ACTION 1.1 ACTION shall be that part of a Specification which prescribes remedial measures required under designated conditions.
AVERAGE PLANAR EXPOSURE 1.2 The AVERAGE PLANAR EXPOSURE shall be applicable to a specific planar height and is equal to the sum of the exposure of all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle.
AVERAGE PLA"AR LINEAR HEAT GENERATION P. ATE 1.3 The AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGrt) shall be applicable to a specific planar height and is equal to the sum of the LINEAR HEAT GENERATION RATES for all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle.
CHANNEL CALIBRATION 1.4 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors.
The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST.
The CHANNEL CALI-BRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.
CHANNEL CHECK l
1.5 A CHANNEL CHECK shall be the qualitative assessment of crsnnel behavior during operation by observation.
This determination shall include, where pos-l sible, comparison of the channel indication and/or status with other indications
- ndhr :t:t;:. d:.-hed f rc: ind: pend:nt in:treent chsnnels r.esuring th: :=
parameter, CHANNEL FUNCTIONAL TEST 1.6 A CHANNEL FUNCTIONAL TEST shall be:
a.
Analog channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alars and/or trip functions and channel fatture trips.
b.
Bistable channels - the injection of a simulated signal into the sensor to verify OPERABILITY including alars and/or t. rip functions.
RIVER BEND - UNIT 1 1-1 i
OEFINITIONS The CHANNEL FUNCTIONAL TEST may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is tested.
CORE ALTERATION 1.7 CORE ALTERATION shall be the addition, removal, relocation or movement of fuel, sources, incore instruments or reactivity controls within the reactor pressure vessel with the vessel head removed and fuel in the vessel.
Normal movement of the SRMs, IRMs LPRMs, TIPS or special movable detectors is not l
considered a CORE ALTERATION.
SJspension of CORE ALTERATIONS shall not pre-clude completion af the movement of a component to a safe conservative position.
CORE MAXIMUM FRACTION OF LIMITING POWER DENSITY 1.8 The CORE MAXIMUM FRACTION OF LIMITING POWER DENSITY (CMFLPD) shall be the highest value of the FLPD which exists in the core.
CRITICAL POWER RATIO
- 1. 9 The CRITICAL POWER RATIO (CPR) shall be the ratio of that power in the assembly which is calculated by application of the GEXL correlation to cause some point in the assembly to ex actual assembly operating power.perience boiling transition, divided by the DOSE EQUIVALENT I-131 1.10 DOSE EQUIVALENT I-131 shall be that concentration of I-131. microcuries per gram, which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present.
The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, "Calculation of Distance Factors for Power and Test Reactor Sites."
1 ORYWELL INTEGRITY 1.11 DRYWELL INTEGRITY shall exist when:
All drywell penetrations required to be closed during accident a.
conditions are either:
1.
Capable of being closed by an OPERABLE drywell automatic isola-tion system, or 2.
Closed by at least one manual valve, blind flange, or deactivated automatic valve secured in its closed position, except as pro-vided in Specification 3.6.4.
b.
All drywell equipment hatches are closed and sealed.
The drywell airlock is in compliance with the requirements of c.
Specification 3.6.2.3.
RIVER BEND - UNIT 1 1-2 Amendment No. 29
TABLE 3.3.1-1 (Cor *.inued)
- =
- gj REACTOR PROTECT 10t2 SYSTEM INSTRtBENTATION E
APPLICABLE MINIMUM OPERATIONAL OPERABLE CHANNELS FUNCTIONAL INIIT CONDITIONS PER TPIP SYSTEN (a)
ACTION E
U 9.
Scram Discharge Volues blater Level - High w
a.
Level Transmitter 1
2 2
1 I8I S
2 3
b.
Float Switches 1
2 2
1 IGI S
2 3
IhI
- 10. Turbine Stop Valve - Closure I
4 6
[
Trip 011 Pressure - Low 1(h) 2 6
- 12. Reacter Mode Switch Shutdown Position 1, 2 2
1 3, 4 2
7 5
2 3
- 13. Manuel Scram 1, 2 2
1 3, 4 2
8 5
2 9
O
)
1
l c
TABLE 3.3.1-1 (Continued)
REACTOR PROTECTION SYSTEM INSTRUMENTATION ACTION ACTION 1 Be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
ACTION 2 Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, verify all insertable control rods to be inserted in the core and lock the reactor mode switch in the Shutdown position.
ACTION 3 Suspend all operations involving CORE ALTERATIONS and insert l
al) insertable control rods within one hour.
ACTION 4 Be in at least STARTUP within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, i
ACTION 5 Be in STARTUP with the main steam line isolation valves closed within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
i ACTION 6 Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, place the inoperable instrument channels in both trip systems in the tripped condition; otherwise, initiate a re-duction in THERMAL POWER within 15 minutes and reduce turbine first stage pressure to less than the automatic bypass setpoint (less than 40% of RATED THERMAL POWER) within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
ACTION 7 Within I hour, verify all insertable control rods to be inserted.
ACTION 8 Lock the reactor mode switch in the Shutdown position within one hour.
ACTION 9 Suspend all operations involving CORE ALTERATIONS, and insert all insertable control rods and lock the reactor mode switch in the Shutdown position within one hour.
ACTION 10 -
Within one hour, place the inoperable instrument channels in both trip systems in the tripped condition; otherwise be in at least STARTUP within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
RIVER BEND - UNIT 1 3/4 3-4 Amendment No. 29
.