ML18025B665
| ML18025B665 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/28/1981 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8110020359 | |
| Download: ML18025B665 (10) | |
Text
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S110020350 OVC ~ DATE'. 81/09/26 NOTARIZED:
NO Browses Ferry Nuclear Power Station.
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1 AFF ILI AT IOV Office of 'luclear Reactor Regulationi Oirector 30 "I"E,T 05000259 34/~~
05700296 SUBJ=CT:
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3, safety analyses for license ecs 161i162 4 163'n r spots to ion-re loss of turoine control oil 1 valve fast closure orovided.
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400 Chestnut Street Tower II September 28, 1981 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Canmssion Washington, DC 20555
Dear Mr. Denton:
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In the Matter of the Tennessee Valley Authority Docket Nos. 50-259 50-260 50-296 T. A. Ippolito's letter to H. G. Parris dated May 29, 1981 requested that we provide additional justification and safety analyses for Browns.<<erry license amendment requests TVA BFNP TS 161, TS 162, and TS 163.
By letter free me to you dated July 13, 1981, we provided this information for proposed amendments TS 161 and TS 163.
The requested information for TS 162 is provided as the enclosure to this letter.
Very truly yours, TEKN1ZSEE VAIZZYAVIKORITY L. M. Mills, Manager Nuclear Regulation and Safety Sworn to axi subscr'h'~day of
~c /0 No Public My 6mrussion Expires Enclosure fore me 1981 oO/
8110020359 810928 PDR ADOCK 05000259 P
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JUSTIFICATION >OR PROPOSED CHANCES TO TECHNICAL SPECIFICATIONS BROWifS FERRY NUCLEAR PLANT (TVA BFNP TS 162)
Units 1 and 2 Pages 8, 9, 10, and 11 Unit 3 Pages 9,
10, 11, 12, and 13 All changes to these pages are either insertion or modification of a title for a subsection or renumbering/relettering changes.
For example, the first change on units 1 and 2,
page 9, is merely the insertion of a letter b.
There are no changes to any safety limits or limiting safety system settings.
Units 1 and 2 Pages 23, 24, 34, 38, 40, and 44 Unit 3 Pages 22, 23, 32, 33, 37, 39, and 43 The changes on these pages are clarifications which combine references to a loss of turbine control oil pressure and turbine control valve fast closure and renames them turbine control valve fast c'osure or turbine trip.
Loss of turbine control oil pressure and turbine control valve fast closure are both detected by the same instrument.
The trip mechanism is pressure switches located downstream of the fast closure solenoid valves.
Either closure of the solenoid valves (indicative of a control valve fast closure) or a loss of control oil pressure will result in a pressure below the setpoint of the switches and therefoxe a
reactox trip.
Since there is actually only one instrument that senses either of the conditions, both of these conditions were combined as a
clarification.
This change does not reflect a physical modification or a change in surveillance requirements.
Since this change is a clarification that reflects actual plant configuration, there is no effect on plant safety.
Units 1 and 2 Pages 33 and 36 Unit 3 - Pages 32, 33, and 35 This change adds note 23 to table 3.1.A.
This note provides clarification to allow the performance of necessary testing without reducing plant reliability.
Safety is not adversely affected because reactor protection functions are still provided by the operable channel in the trip system being tested and the other trip system.
Units 1 and 2 Pages 40 and 41 Unit 3 Pages 39 and 40'his change replaces "shutdown" with "startup." It is a clarification that fixes the frequency of required testing.
Present technical specifications specify a maximum frequency but are unclear on a minimum frequency.
This change would fix the frequency at once each operating cycle.
Units 1 and 2 Page 53 Unit 3 Page 55 This change replaces reference to 6.7.3.D with the coxrect reference 6.7.3.C.
Reference to 6.7.3.D is incorrect.
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Units 1 and 2 - Pages 55, 56, 57, 58, 59, and 61 Unit 3 Pages 57, 58, 59, 60, 61, and 63 This change would add the same note described above (units 1 and 2 pages 33 and 36; unit 3 pages 32, 33, and 35) to table 3.2.A.
Units 1 and 2 Page 74 Unit 3 Page 77 This change is a clarification to a footnote.
No actual technical specification requirement is changed.
Units 1 and 2 Page 78 Unit 3 Page 81 Instrument scales on reactor water level instruments LE-3-46A and B were changed to reflect current plant instrumentation.
The actual range covered is not changed.
Units 1 and 2 -'age 121 Unit 3 Page 120 This change allows testing to determine possible collet housing failure before attempting to insert rods incapable of normal insertion as required in the LCO section.
This change resolves ambiguities between LCO specifications and surveillance specifications.
Attempts to insert rods with failed collet housings could cause additional damage to the housings.
Units 1 and 2 Page 173 Unit 3 Page 183 This change adds a label to the ordinate of Figure 3.5.2. It does not affect the actual curves.
Units 1 and 2 Page 175 Unit 3 - Page 185 This change provides additional guidance with regard to curve 2 of Figure 3.6-1 and removes.existing ambiguities.
Units 1 and 2 Pages
- 176, 177,
- 178, and 179 These changes make units 1 and 2 technical specifications, sections 3.6.B and 4.6.B, consistent with unit 3 specifications.
'I Units 1 and 2 Page 180 Unit 3 Page 191 This change would allow the air sampling system to be temporarily removed from service for testing and calibration without using portable monitors as replacements.
This change is a clarification.
Present technical specifications do not require the use of portable monitors when the air sampling system is unavailable.
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Units 1 and 2 Page 182 Unit 3 Page 195 This change adds a surveillance requirement required by LCO 3.6.F.3.
Also, the unit 3 change relocates an LCO.
There is no actual cnange to the LCO.
Units 1 and 2 Page 235 Unit 3 - Page 245 This change replaces weight percent with volume percent.
This makes the technical specifications consistent with the FSAR.
The change is in the conservative direction; therefore, plant safety is not affected.
Units 1 and 2 Page 293 In this change, the frequency of battery-rated discharge tests for units 1
and 2 is changed from 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to 24 months.
The present specification contains an obvious clerical error and is being changed to the frequency in the unit 3 specification.
Unit 3 Page 326 This change is a clarification for the LPCI ifG set technical specification.
This change provides consistency between 3.9.C.3 and 3.9.C.4 and relates the requirement for NG set operability to the appropriate RHR system technical specification.
This change is a clarification and does not affect safety.
Units 1 and 2 Pages 302 and 303 Unit 3 Pages 332 and 333 This change replaces
%5K with '%AK/K.
This corrects a clerical error.
Units 1 and 2 Page 319 Unit 3 Page 351 This change corrects a clerical error by changing "d" to "c".
Units 1 and 2 Page 356 Unit 3 Page 386 This change adds reporting requirements for seismic and meteorological data.
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