ML20207F763
| ML20207F763 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry, Sequoyah  |
| Issue date: | 03/02/1999 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20207F768 | List: |
| References | |
| NUDOCS 9903110325 | |
| Download: ML20207F763 (6) | |
Text
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ENCICSURE 4 TENNESSEE VALLEY AUTHORITY SEQUOYAH PLANT (SQN)
UNITS l'~AND 2 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE TS-98-05 MARKED PAGES I.
AFFECTED PAGE LIST Unit 1, DPR-77, page 8 Unit 2, DPR-79, page 6 II.
MARKED PAGES See attached.
s 9903110325 990302
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PDR ADOCK 05000259 i P
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E4-1
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(1 91 6 TNe omndtion le denseed.
l IM9 (20)
Law Ta =. ----- overar--. Pr-ww rsmenen 3 2 21 At the tret autage of sufneens alierstion tout ne later then stersup fe8 ewing the seeend reNeung outage. TVA shen 6noted en overpressure nutgesen eyetem wtdeh meses IWIC requiremente.
R27 (213 canual med Am TN=him ftaedan 4_21 Peter W esereup sher flret rebelhg. TVA sher euberut the estesle of the inspeeden preerem for coentres red guide th.mele twee won weer for NAc esprever.
123) tut * " - pian por r-
- c._c Each of the fedewhsg cafwDnene shell be como6eted to the sedefecten of the NAC by the times indiossed A.
Eafarv 2.2:: 22 Graue <<*a 99 9 I a 1.21 6
( % Cand.hanen dalded 3 Pner se Av
-cent er, TVA equir o have Set up.
wiu v e ad esy of S
l ing and he; _
l 3.
thart.Tarm A: :in: Analveis and Praedes seveien Ita +n ?? 7.tc.gl Within thwty effecdve fuS power days, TVA chall revise Emergency Opereeng Precedurie end Dnet the sporetore en the revisten.
I C.
camrat sammn-% rewa. tr,, e 1, TVA shed oenender the benefits of instading date recordng end legging l
equipment in the eenered reem to carrect une esfaciencies asese6eted esteh M27 I
the trendng of important parametere en strie chart recordere uwd in the i.ontrol seem se part of the Detened Centree Room Design Review,,nenia.ori ehe i
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Amenntnant 23,'"a35
^=su*' 88-DPR -77 E4-2
l
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(13) Fira Protection Tvh shall inglement arkt amintain in effect all provisions of the approved fire prctection program referenced in Sequoyah Nuclear plant's Final Safety Analysis Report and as approved in NRC. Safety Evaluation Reports contained in WUREG.0011, supplements 1, 2, and 5, NUREG 1232, volume 2. NRC letters R21s dated WV 29, and October 4.1986, and the Safety Evaluation it.eued on August 12, 1997, for License Amendment No. 214, subject to the following provisions TVA may make changes to the approved fire protection program without prior approval of the Consulssion only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
(14) f, an14 mara with tamilaterv Guide 1. 97 Tvh shall implement modifications necessary to comply with Revision 2.of Replatory Guide 1.97, ' Instrumentation for I.ight water Cooled Nuc. ear Power plants to Assess Flant Conditions 845 During and Following an Accident," dated December 1980 by
.startup from the Unit 2 Cycle 4 refueling outage.
(15) carromian of carbon staal minino TVA shall carry out a surveillance program on corrosion of carbon steel pipir.g in accordance with TVA document SQRD.50 328/03-10 dated August 25, 1981, and procedures for implementation are to be submitted for NRC concurrence by October 15, 1981.
(16) wtmaa.0727 caaAltions (section 21.2)
Each of the following conditions shall also be performed to the 22 satistsetion of the NRO:
T' chnical Mviser (section 21.2.
f.A.1.11 a.
Shift a
TVA s' hall provide a fully trained on.shif t technical advisor to the shif t operations supervisor.
l Riff b.
Ta b -daae safety rneinserine aroue (section 22.2.
' ^ ^
("Th Mie is dele 11 havey onsite Iptiepender/SafetAginMrig TV l
l 1
Agust 12, 1997
)
Amendment pos. 45, 159, 218 i
~m bP0-N)
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ENCLOSURE 5 TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT (SQN) 1 UNITS 1 AND 2 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE TS-98-05 REVISED PAGES I.
'AFFECTED PAGE LIST
' Unit 1, DPR-77, page 8 Unit 2, DPR-79, page 6 II.
REVISED PAGES See attached.
i l
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.I ES-1
F.
. (15)
Mechanical Snubbers This condition is deleted.
l R239 (20)
Low Temnerature O*veroressure Protection (Section 5.2.2)
' At the first outage of sufficient duration, but no later than startup following the second refuelme ef._%, TVA shall install an overpressure mitigation system which meets NRC requirements.
R27 (21)
Control Rod Guide Thimble iSection 42 Prior to startup after first refueling, TVA shall submit the details of the inspection program for control rod guide thimble tube wall wear for NRC approva!.
(22) TMI Action Plan Full-Power Conditions Each of the folicwing conditions shall be completed to the satisfaction of the
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NRC by the times indicated:
A. Safety Enoineerino Group (Section 22.2.1.B.1.21 This condition is deleted.
l B.
Short-Term Accident Anal" sis and Procedure Revision (Section 22.2.1.C.11 Within thirty effective full-power days, TVA shall revise Emergency Operating Procedures and brief the operators on the revision.
C.
Control Room Desion (Section 22.2. l.D.11 TVA shall consider the benefits of installing data recording and logging equipment in the control room to correct the deficiencies R27 associated with the trending of important parameters on strip chart recorders used in the control room as part of the Detailed Control Room Design Review. Implementation shall be carried out in accordance with SECY 82111B.
Amendment 23, 235 E5-2
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(13) Fire Protection TVA shall implement and maintain in effect all provisions of the approved fire protection program referenced in Sequoyah l
Nuclear Plant's Final Safety Analysis Report and as approved in NRC Safety Evaluation Reports contained in NUREG-0011, Supplements 1, 2, and 5, NUREG 1232, Volume 2, NRC letters R218 i
dated May 29 and October 6,1986, and the Safety Evaluation Issued on August 12,1997, for License Amendment No. 218, i
subject to the following provision:
TVA may make changes to the approved fire protection j
program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
(14) Comoliance With Reaulatorv Guide 1.97 TVA shallimplement modifications necessary to comply with Revision 2 of Regulatory Guide 1.97. " Instrumentation for Light Water Cooled Nuclear Power Plants to assess Plant Conditions R45 During and Following an Accident," dated December 1980 by startup from the Unit 2 Cycle 4 refueling outage.
(15) Corrosion of Carbon Steel Pinino TVA shall carry out a surveillance program on corrosion of carbon steel piping in accordance with TVA document SORD-50 328/81-10 dated August 25,1981, and procedures for implementation are to be submitted for NRC concurrence by l
October 15,1981.
(16) NUBEG-0737 Conditions (Section 22.2)-
i Each of the following conditions shall also be performed to the satisfaction of the NRC:
R2 a.
Shift Technical Advisor (Section 22.2. l.A.1.11 TVA shall provide a fully-trained on shift technical advisor to the shift operations supervisor.
l R169 b.
Indeoendent Safety Enaineerino Groun (Section 22.2. l.B.1.2)
This condition is deleted.
l Amendment Nos. 45,169,218 E5-3