ML20153D474
| ML20153D474 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 08/29/1988 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20153D479 | List: |
| References | |
| NUDOCS 8809020220 | |
| Download: ML20153D474 (7) | |
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
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%,.....,o GULF STATES UTIL: TIES COMPANY DOCKET NO. 50-458 RIVER BEND STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 26 License No. NPF a7 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
"ihe application for amendment by Gulf States Utilities Company (thelicensee)datedMay 31, 1988, complies with the standarde 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 1; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance:
(i) that the activities authorized by this an,endment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this licenso amendment will not be inimical to the confon 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 Comission's regulations and all applicable requirements have been satisfied.
G809020220 880829 PDR ADOCK 05000458 P
. 2.
Accordingly, the license is amended by clianges to the Technical Specifications as indicated in the attachment to this license amendment andParagraph2.C.(2)ofFacilityOperatingLicenseNo.NPF-47ishereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 26 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. GSU shall operate the facility in accordance with the Technical Specifications and the Environmental Protaction Plan.
3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION p:
- a. Gk
.-Jose A. Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 29, 1988 4
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ATTACHMENT TO LICENSE AMENDMENT NO. 26 FACILIT_Y OPERATING LICENSE NO. NPF-47 DOCKET NO. 50-458 Replace the following pages of the Appendix "A" Technic?1 Specifications with the enclosed pages. The revised pages are identified *, Amendment number and conta'n vertical lines indicating the area of change. Overleaf pages provided to maintain document completeness.
REMOVE PAGES INSERT PAGES 3/4 1-4 3/4 1-4 3/4 1-5 3/41-5(Nochange, reissued due to repagination)
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REACTIVITY CONTROL SYSTEMS 3/4.1.3 CONTROL RODS CONTROL ROD OPERABILITY LIMITING CONDITION FOR OPERATION 3.1.3.1 All centrol rods shall be OPERABLE.
APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.
ACTION:
With one control rod inoperable, due to being immovable as a result of a.
excessive friction or mechanical interference, or known to be untrippable:
1.
Within one hour:
a)
Verify that the inoperable control rod, if withdrawn, is separated from all other inoperable control rods by at least two control cells in all directions.
b)
Disarm the associated directional control valves
- either:
1)
Electrically, or 2)
Hydraulically by closing the drive water and exhaust water isolation valves.
Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
2.
Restore the inoperable control rod to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
With one or more control rods trippable but inoperable for causes other than addressed in ACTION a, above:
1.
If the inoperable control rod (s) is withdrawn, within one hour:
a)
Verify that the inoperable withdrawn control rod (s) is separated from all other inoperable withdrawn control rods by at least two control cells in all directions, and b)
Demonstrate the insertion capability of the inoperable withdrawn control rod (s) by inserting the control rod (s) at least one notch by drive water pressure within the normal operating range **.
"May be rearned intermittently, under administrative control, to permit test-ing associated with restoring the control rod to OPERABLE status.
- The inoperable control rod say then be withdrawn to a position no further withdrawn than its position when found to be inoperable.
RIVER BEND - UNIT 1 3/4 1-3
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REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)
ACTION (Continued)
Otherwise, insert the inoperable withdrawn control rod (s) and disarm the associated directional control valves
- either:
a)
Electrically, or b)
Hydraulically by closing the drive water and exhaust water isolation valves.
2.
If the inoperable control rod (s) is inserted, within one hour disarm the associated directional control valves
- either:
a)
Electrically, or b)
Hydraulically by closing the drive water and exhaust water isolation valves.
Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
3.
The provisions of Specification 3.0.4 are not applicable.
c.
With more than 8 control rods inoperable, 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 />, d.
With one scram discharge volume vent valve and/or one scram discharge volume drain valve inoperable and open, restore the inoperable valve (s) to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
e.
With two scram discharge volume vent valves and/or two scram discharge volume drain valves inoperable and open, restore one valve in the vent line and one valve in the daain line to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and restore all valves t) OPERABLE status within the next 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> or close at least one ven valve and one drain valve and be in at least HOT SHUTOOWN within ihe next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
f.
With any scram discharge volume vent val 'e(s) and/or any scram discharge volume drain valve (s) inoperable and closed except when required by ?CTION statement e. above, restore all valves to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least HOT SHUT 00WN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.1.3.1.1 The scram discharge volume drain and vent valves shall be demonstrated OPERABLE by:
a.
At Isast once per 31 days verifying each valve to be open,** and "May be rearmed intermittently, under administrative control, to permit testing associated with restoring the control rod to OPERABLE status.
- These valves may be closed intermittently for testing under administrative controls.
RIVER BEND - UNIT 1 3/4 1-4 Amendment No. 26
REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.
At least once per 92 days cycling each valve through at least one complete cycle of full travel.
4.1.3.1.2 When above the low power setpoint of the RPCS, all withdrawn control rods not required to have their directional control valves disarmed electrically or hydraulically shall be demonstrated OPERABLE by moving each control rod at least one notch:
a.
At least once per 7 days, and b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when any control rod is immovable as a result of excessive friction or mechanical interference.
4.1.3.1.3 All control rods shall be demonstrated OPERABLE by performance of Surveillance Requirements 4.1.3.2, 4.1.3.3, 4.1.3.4 and 4.1.3.5.
4.1.3.1.4 The scram discharge volume shall be determined OPERABLE by demonstrating the scram discharge volume drain and vent valves OPERABLE, at least once per 18 months, by verifying that the drain and vent valves:
a.
Close within 30 seconds after receipt of a signal for control rods to scram, and b.
Open when the scram signal is reset.
RIVER BEND - UNIT 1 3/4 1-5 Amendment No. 26
i REACTIVITY CONTROL SYSTEMS CONTROL ROD MAXIMUM SCRAM INSERTION TIMES LIMITING CONDITION FOR OPERATION 3.1.3.2 The maximum scram insertion time of each control rod from the fully withdrawn position, based on de-ene:gization of the scram pilot valve solenoids as time zero, shall not exceed the following limits:
Maximum Insertion Times to Notch Position (Seconds)
Reactor Vessel Dome Pressure (psia)*
43 29 13 950 D731 0.81 1.44 1050 0.32 0.86 1.57 APPLICABILITY:
OPERATIONAL CONDITIONS 1 and '.
2 ACTION:
With the maximum scram insertion time of one or more control rods a.
exceeding the maximum scram insertion time limits of Specifica-tion 3.1.3.2 as determined by Surveillance Requirement 4.1.3.2.a or b, operation may continue provided that:
1.
For all "slow" control rods, i.e., those which exceed the limits of Specification 3.1.3.2, the individual scram insertion times do not exceed the following limits:
Maximum Insertion Times Reactor Vessel Dome Pressure (psia)*
_43 29
_13 950 0.38 1.09 2.09 1050 0.39 1.14 2.22 2.
For "fast" control rods, i.e., those which satisfy the limits of Specification 3.1.3.2, the average scram insertion times do not exceed the following limits:
Maximum Average Insertion Times to Notch Position (Seconds)
Reactor Vessel Dome Pressure (psia)*
43 29 13 950 U
U I"T5 1050 0.31 0.84 1.53 3.
The sum of "fast" control rods with individual scram insertion times in excess of the limits of ACTION a.2 and of "slow" control rods does not exceed 5.
"For intenmediate reactor vessel doet pressure, the scram time criterion is determined by linear interpolation at each notch position.
RIVER BEND - UNIT 1 3/4 1-6
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