ML20043A700
| ML20043A700 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 05/17/1990 |
| From: | Johari Moore NRC OFFICE OF THE GENERAL COUNSEL (OGC) |
| To: | Anderson G, Bloch P, Johnson E Atomic Safety and Licensing Board Panel |
| References | |
| CON-#290-10376 OLA-5, NUDOCS 9005230002 | |
| Download: ML20043A700 (12) | |
Text
< - -
k s '/
- 3,,, -.%[%
UNITED STATES I
NUCLEAR REGULATORY COMMISSION 00CKt1ED USOC j; -.
h
!l WASHINGTON, D. C. 20555
[
May 17, 1990 g g 21 hB 23
....+
ancr :r 9'#y"+Q" -
y;m;;
Peter B._Bloch, Chairman Elizabeth B. Johnson Administrative Judge Administrative Judge Atomic Safety and Licensing Oak Ridge National Laboratory Board Panel P.O. Box 2008 U.S. Nuclear Regulatory Comission Bethel Valley Road Washington, DC 20555 Building 3500, Hail Stop 6010 Dak Ridge, Tennessee 37830
-George C. Anderson Administrative Judge
.7719 Ridge Drive, N.E.
Seattle, Washington 98115 in the Matter of FLORIDA DOWER & LIGHT COMPANY (Turkey Point Plant, Units Nos. 3 and 4)
Technical Specifications Replacement Docket Nos. 50-250-OLA-5, 50-251-OLA-5
Dear _ Administrative Judges:
-This letter is to inform the Board that on May 15, 1990, the Staff published its proposed determination that the amendment which is the subject of this proceeding does not involve a significant hazards consideration. A copy of-the Federal-Register notice is attached for your information. This notice is also being served on the parties to this proceeding.
Sincerely, WW Q MO Janice E. Moore Counsel for NRC Staff Enclosure cc: w/
Enclosure:
Service List 9005230002 9005j7 gDR ADocg osooop3g 3gg}
eda
-. _. - ~.
j g
30218 Federal Registr / Vol. 55, No. 94 / Tuesday, May 15, 1990 / Notices have a significant effect en the quality Units 3 and 4. located in Dade County.
of the human environment.
=
For further details with respect to the Florida. The Commission is now issuing Administrative changes are non.
technicalin nature and are intended to action see 1) the application for its Notice of Proposed No Significant amendmen(t dated May 20.1988, as Hazards Consideration in accordance make the TS easier to use for plant -
supplemented November 27.1989,(2) with to CFR 50.91 and 50.92.
operations personnel.
Amendment No. 29 to Ucense No.NPF.
The proposed amendments would More restrictive or more complete replace the current (custom Technical requirements are either more 58, (3) the Commission's related SafetySpecifications (CTS), which)are part of conservative than corresponding Evaluation dated May 7.1990, and (4) the license issued in the early 1970's, requirements in the CTS, or are the Environmental Assessment dated with a set of revised Technical additional restrictions which are not in April 27.1990(55 FR 18990). All of these Specifications items are available for public inspection Standard Techn(RW) based on the staffs the CTS. The more restrictive or more at the Commission's Public Documentfor Westinghouse-designed reactors.ical Specifications (STS) complet Room, Gelman Building,2120 L Street enhancement The CTS and the RTS consist of 6 parts Any relaxations of selected existing NW and at the Perry Public Ubrary, as follows:
3753 Main Street, Perry, Ohle 44081. A copy ofiterns Port 1-Definitions requirements are based on many obtained upon(2),(3) and (4) mey bePart 2-Safety Limits and Limiting Safety reactor years of operating experience in the n ar eac orin s request addressed to the Settinge p,9 U.S. Nuclear Regulatory Commission.
Part wumiting Conditions for Operation provide !]ttle or no safety benefit are Washington DC 20555, Attention, fLCOs)
Director, Division of Reactor Proje' cts III, Pan emanu Requimments counterproductive and may justifiably IV. V and Special Projects.
be eased or removed from the CM. In Pa tk-Ad a ve Controla I
Dated at Rockville, Maryland this 7th day It should be notedin reading the RTS
[ady e ls i
'N8F
- n ha e For the Nuclear Regula tory Commission.
that Parts 3 and 4 are presented as an previously been issued in TS for other John N.Hannon.
Integrated unit, so that the LCO and the plants.
Director. Project Directorate llI.J, Division of surveillance requirement for a given Deletion of selected requirements is ReactorProjects-111. /P, FondSpecial plant system (or TS Section) are described on page G-1 of Appendix A of Prefects ficeofNuclearReactor presented together, system by system 1of the Application
'8 (or Section by Section).
Deletions consist of:(1 Requirements
[FR Doc. 90-11262 Filed 5-14-a0; 815 am] The licensee's amendment application determined not to be ne)ede (the Application submitted on June 5, purposes, and (2) n ements wM amo cooe team 1989, as supplem)ented on November 3, already exist in som@e other controlled (Docket Nos.80-250 and 50-2611
_ 1989, and May 1,1990, included four document.
attachments. Attachtr.entIincludes thein the supplementaldocument proposed RTS and revised bases to submitted by the licensee on May 1, Florida Power and Ught Co.; Proposed support the RTS. Attachment 11is the no Significant Hazart)s Consideration 1990, the changes evaluated for No licensee's safety evaluation, and Significant Hazards Consideration Determination Appendix A of Attachment IIis a (Appendix A of Attachment 11of the On December E 1989, the U.S. Nuclear supplement to the safety evaluation andApplication) are summarized and Regulatory Commission (the provides the No Significant Hazards orga nized into tabular form. The table.
Commission) published in the Federal Evaluation. Attachment 111 identifies entitled " Categorization of Changes to Register a notice announcing FSAR changes planned to keep the the Current Tech Specs"is provided consideration ofissuance of license FSAR and RTS consistent with eachhere for clarification as Table 1. The amendments to revise the Technical other. Attachment fVidentifies certain table includes no new information, but Specifications (TS) for Turkey Point safety improvements,in response to lists and organizes all the changes.The Units 3. and 4. Florida Power and Lightseparate NRC initiatives, which will be first column of the table lists the new Company, Consideration ofissuance of implemented as a result ofimplementing RTS section that results from the Amendments to Facility Operating the RTS. Attachment IV was provided to changes to the CTS.The sec Licenses and Opportunity for Hearing. assist the NRC in tracking progress on of the table lists the CTS sections being these otherinitiatives.
V. 54, FR 50295 (December 5,1989).
The Commission is considering Throughout Appendix A of changed. The third column lists the page issuance of amendments to Facility 1 to the Application, the referencein Appendix A ofAttachment licensee has ch IIof the Application where the changes Operating License Nos. DpR-31 and TS changes as:aracterized the proposed are described and evaluated for No DpR 41 issued to Florida Power and (1) Administrative non-Light Company (FPL, the licensee) for technical), (2) more restrictive or m(ore Significant Hazards Considerations. The operation of the Turkey Point Plant, complete. (3) relaxations, and (4) last four columns list the changes, by deletion of selected requirementa.
category, using the notation from Appendix A.
TABLE l-CATEGORIZ20N OF CHANGES TO THE CURRENT TE Cun M toe spec, W Category esformaton from NSH for revised W.at bpeerncasons R
m spec. %
NSH appenda A page Administraeve veterences changes Che that are De6etone from the f
atone current lectL spece.
1.0__....,--
1.0 and Tat 9e 41-1 --
1-1 evy 1 J 14. 3 o5, and B3.o$.
..! 1-4 thru 1 _
A2a 1.2.3AS.a... M)b. --. None.._
MK1.2.3.4.5,e.7.a 1 17-M12a 7.a.s.10.11 m
_.J A2.
J M) ~..- J M) --
M)c.s.10.11.12.13.
l None.
.f 4
Federal Regiskr / Vol. 55. NA 94 / Tuesday. May is.1990 / Noticcs -
arts
' TAsLE 1. -CATwoonizATsoN OF CHANGES TO THE CupmEW TEO4. SPECS.--Cottunued
.F outegory WWorraemon from NSH for rewteed techrucel spooWiestone jt Neuised telfLMost No. -
Cuness ledh spec. ftM ' gQ,,y,ng, g,,
g,,,,,,,,,,,
idore esmptsee put are Ostseors trom the p
" 8' roterenese cheriges tons.
cwrent tech. space.
' 2.t.1
' 1.1. 2.1 and 82.1 3-1 suo 2-2 U)a.
'A. fib.12 None Nose.
. 3.1J 1.1. IA and B2.2 24 swu 2 4 M).a A.2)b.-
Nous None.
3 8J.1 1.3 t-6 thru t-7 MLa -
M)D.1.2 A.5 et None.
3/40 3 0. 4.0, and B3.0 3/4 0-19wu 3/4 6 A.24 M)b.1 M) 4.12 None.
4.0.1 and No? Wa*.-
Throughed Space.
S/4 0-6 thru 3/4 04-ARLs None Ulb. _
- None, t
32.1.t. 3.2 4.c. TetWe 3/41 1 Svu 3/414-A2) e Mh113 AJ)A1AJ
'None.
- 8/4.1.1.1 4.1 2, hem 1.e,4.11, 4
and6S.& m.
8/4.1.1.2 TatWe 4.1-3 llem 1.s 3/414 vvu 3/414-M)e MIb.113 =
Nono _
'None.
3/4.1.1J 3 IJ.1 3/4 b7 thru 3/414-M) e.
MA fens None. -
. S/4.1.1.4 None. Asse ?osu 3/41-0 svu 3/41 10 M)4 A2lb.
eMatart S/4.1A1 SAa. Teels 4.1 1 here 3/4 b11 syv 3/41 43 MW A2ltL1J M)A None.
s
- 19. and TatWe 4.16-1 nem S, 8/4.112 8 es. 3 6.bJ,3.6.6 4 3/4 bid swu 3/41 A2)4_
' M)b.12 AJM.113.4A
' Mure. '
3 6 c1 SA.c 4 3A 42 and TetWe 4.16-1 Rom 8.
3/4.12.3 '
3 6.b.1. 3.6A1. 3 6 ILt.
3/41-10 svu 3/4141 M)4 AJE113 MIA1.tJ
. None. '
and TatWe 4.1 1 mems 12 aruf 16.
iJ 3/4.124 TatWe 4.b1 tem 44 and 3/4 S-22 Swu 3/41-44 A2)4 _
Mitk1A3 A.2ke.1J None.
TatWe 4.ht hem 3.
3/4.1.2A -
3 4.1 a.1. 3.6.b.3. 3.6.b 6.
3/4 $46 thru 3/4 b29. A.2).a A2)th?A3 A.2)A143 N one.
3.sc.3.3 Sat.and TatWe 4.12 meme I and 3.
3/4.126 3 6.tL6. 3.&c.6. 3.6.d.
3/4 b30 thru S/4142. A2).a _
M)tkt.2 A.2)A
- None, and TatWe 4.161 mem 6.
3/4.1.3.1.
3.2.2. 3 3 da. 3.2.46.
3/4143 tvu 3/4146 M).4 M)tL1A3 M)At13A6 None.
3 2.5 and TatWe 4.14 Mem &
3/4.1.3.2 3 2.6, and Tabis 4.1 1 3/4147 tvu 3/4149 M).e A.2)tL12.
A2).t.1.2 Mons.
Rome 0 and 10.
l ^
3 /4.1.3.3 TetWe 4.bi tem 9 3/4 b40 thru S/4 b41 A2ka -
U g1AJ Noes None.
l 1-3/4.1.34 3.2.3 and TatWe 4.12 3/4142 tvu 3/4 b43 M).a A2)tL1A None-None.
lc hem 6.
3/41.36 3.2.1.s 3/4144 thru 3/41 A.2) e MitL113,_
3/4.1.3 6-3.2.1 b. 3.2.1.c. 3.216.
3/41-46 thru 3/41-47 M).e M)b.12__
M)r None.
3.2.1.g -
3/4.2.1.
SJA.c evu 3.2Ag and 3/4 21 thru 3/4 3 A.M.e AJ)tti,2 M)r None.
3.2.6.
4 3/4.2J 3 2 6 a. 3.2.6.b, and 3/4 2-4 thru 3/4 2-6 M).4 None A2)tt None.
Table 4.1-1 Rom ib.
3/4.2.3.
3.2 6.a. 3 2.6 b, and 3/4 24 thru 3/4 24 M).a A2)tk.
M).c. _
None.
Table 4.1 1 hem Ib.
-3/4.24 3.2.6h end 12 ei 3/4 24 thru 3/4 212 Mts M* 12.3.4 A.2Lc.12_
None.
L, t
3/4.2.6 -
3.1.6..
3/4 2-13 thru 3/4 214_ A2).a M)D.1.2.3 kone -
None.
l-3/4.31 3 61 and TatWe 4.1 1 3/4 3-1 #wu 3/4 34 A21a M)b 13 A2)*113,4,6 None i+
3/4.3.2-3 6. Table 3.6-2. TotWe 3/4 3-6 thru 3/4 3 A2).e A.2)t.113.4 A2Kc.12.3 None.end page 1 3 6-3. TatWe 3.6-4 and TatWe 4.ht.
3/4.3.3.1 TetWe 3.6-3 loom 4 3/4 3-14 thre 3/4 3.t3. A2).e -
M)tL11A4A6. AJ)A1J None. -
- TetWe 3.6-4 tem 10, TatWe 4.1 1 Items 16A 100. Sea. Seb.
and TetWe 3 6-6 lesme 13e and 13b.
3/4.3.32 3.2.7 3/4 3 44 thru 3/4 316 A.2) e -
A.2)tti.2.3.4 None None.
+
3/4.3.3.3 TatWe 3.6-6 home 1 tNru 3/4 3-14 evu 3/4 319. AF).a.12.-.
M)bA2 MSc.1J None.
% and 13 thru 16, TetWe 4.b1 home 6 15A,tSB.td.17A.
178.26,27,26.29.
30.34,36.36,37,30,
- 39. and 40.
3/4.3.34 -
3.14.1 and 4.16.1 ft/4 3-20 thru 3/4 342. M) a M)b.1 A2)A1J-.. None.
3/4.3.3 6--
3.01.C.TatWe 3D-2 and 3/4 3 A2)a Nore None.
None.
TatWe 4.1 3.
3/4.3.36
. 3.t 2.C. TatWe 3 S-3.
3/4 344 thru 3/4 3-26. Ml.a M1b.1.2.3.4. _.. None None.
TetWe 3D-4. and A2k6.6.7 _.
TatWe 4.1 4.
~ ~ ~ -
. m..
L,, 2
- n L.PM... '_[ [ a_[ $..#.C_,.._._ _ _ _ _
m 30220 FederB1 Regl6ter /.W: ~1. 55, No. 94 / Tuisday, May..
15, 1990 / Noticas TABUE l.--CATEQOmZATXW OF CNANGES TO THE CURRENT TECH. SPECS.-Continueld e
Com Dilormahon trom NSH tor fewtead techrocal speelhostorie Rodsed teopt spec. No.
Curierit toch spec No(s).
NSH apperuhr A page Aanrustrasve 64cro congdeto
- ist are Deletorie tem Bie selerenose changse 8'g" awrent tectL spect 3/4.411 31 1 A1, 3.1.1 A3.
3/4 4-1 Wyu 3/4 4-3_ A2)4 A2)tk A.MA None.
31 1 A4. 3 4 it, and Tales 4.14 horn it.
3/44.12 3.1.1 AS. 3.416. and 3/4 4-4 Deu 3/4 44_ A2).e A.2)tt None None.
TatWe 4.12 3/4.4.12 123. 31.1 A2. 311 A6.
3/4 44 tou 3/4 4-7_ M)4 A2)tt None None.
3 41.0, and Telde 4.1 2 mem 18, 3/4.4.1.4.1 3114A 3.1.1 AS.
3/4 44 tvu 3/4 4 A.2)a A2)tt A2)A12.3 None.
3 4.1.e, and Tatdo 4.1 i
2 hem it.
3/4.4142 3.1 1.813 4.1.e. and 3/4 4-119vu B/4 4-13 A.2)4 A2)tt A2)A12 None.
Tatne 4.12 hem it.
3/4.411 3.1.1 A1 TatWe 4.1-2 3/4 4-14 Svu 3/4 4-17 A2)e A2)tt1.2.3.4 M)A1A3 None.
Nem 6. and B311 3/4412 3.1.1.c1 Tatdo 4.1-2 3/4 4-18 tvu 3/4 4-19 A.2)4 A2)tL1A3 None None.
nom 6. and 83.11 3/44.3 3.1 1.cl 3'4 4-20 tru 3/4 4-21 M)4 A.2A113 None Norte.
3/444 3.1141. 311e1 and 3/4 o-22 piru 3/4 4 A2).a M)tt A3)A.tk None.
31.1 A3.
3/44.6 4.2.6 3/4 4-95 Wiru 3/4 4-26 A.2La A2ltL12.3 None None.
3/44.41 3.13 f. B31.3, Tatdo 3/4 4-27 vvu 3/4 4-30_ M)4_
M)tL1 A3-M)A None.
4.1-1 tem 20.
3/44.6.2 313e. 31.StL 313c.
3/4 4-31 vvu 3/4 4 M)4 A2)tL1.2.3.4.6 -. A.2)A1A3 None.
31.3d. 31.3e, 81.30 3.16,4.17, and TatWe 4.1-2 Nem 11.
3/44.7 3.1.6 and Tatdo 41-2 3/4 4 35 vvu 3/4 4 A2)4 A2)tL12 A2)A None.
hem ib.
3/448 -
314. B314 and TatWe 3/4 4-38 vvu 3/4 4 A.2).e A2)tL12 M)A12 None.
4.1-2 nem 1.
3/4461 31 A B3.114.20. and 3/4 4-41 #wu 3/4 4-42.
M).a A2)tt12 A2)A t None 84.20.
3/4402 31.2 and B31.2 3/4 4-43 Svu 3/4 4-44..
M)4 Mg12 None None.
3/44.8.3 315,4.16. 8316 and 3/4 4-45 thru 3/4 4-47 A.2)4 A2)tL12A4 None None.
84.16.
3/4410 4.2 and.1.3 3/4 4-46 #wu 3/4 4-49.-. A.2).a M)tt None None.
3/4 4.11 31.1.f. 416. 83.1.1 and 3/4 4-50 thru 3/4 4-61 A2)4 None None None.
84.19.
3/4.61 3 4.1 A3. 3 41b 1, 3/4 6-1 tvu 3/4 6-3_. A.2) e A2)b.12A4.6_ M)A1,2 None.
4.6.2 tL3, TatWe 4.1 1 Rem 21. and TatWe 4.1 2 hem 10.
3/462 3 4.1.4 4 thru 3 4.147 3/4 6-4 evu 3/4 6-9_ A2)4.
A2)b.12A4AS A.2)A1 A3,4,5.6.- None 3 41.b13 4.1.0 4 thru g
3 4.1.tL7. 4 6.1. 412a.
4 6Ab 1. 4.522.2.
4 6.2 b 4. and Tatne 4161 Rome 1 and 2.
3/4.5.3 None. Adde New 3/4 6-10 thru 3/4 6-11 A.2).e A2)D.12,3 None None.
Specrheatiort 31464 3 41 At and TatWe 4.1-3/4 6-12 thru 3/4 613 A214 A2)b.12.3 A.2)A None.
2 mem 2.
3/4611 3.31 3/4 6-1 vvu 3/4 b2._ A.2).a A2)b.1.2.3 A2)A None.
3/4412 4 4.1. 4 4.2. and 4 4.3_
3/4 6-3 Wru 3/4 6-4_ A2).a 4)D.1A3 None None.
3/46.1.3 3 3 4 end 4 42.
3/4 6-6 Uru 3/4 6 6_ A2).a A2)tL1A3 None None.
3/4614 3.32 3/4 6 ? thru 3/4 6-6_. M).a A2)tt None None.
3/46.1.6 None. Adds New 3/4 6-0 thru 3/4 6-10 _ A2)4 --
None None None.
Soeottetiort 3/461.6 4 4.6. 4 4 6, and 4 4.7 3/4 6-11 thru 3/4 6-12-.. A2)4 A.2) b12A4.5-None None.
A.2)A6.7.0 3/461.7 313 and 4 42 3/4 6-13 thru 3/4 S.14
. A.2).a A2g1JA4A_ None None.
a 3/4621 3 4 2,4 6. Table 4.16-1 3/4 6-16 thru 3/4 6-10 A.2).a A2)tLIA3 A.2)A1.2,3 None.
Nem 4 3/4 b22 3 4.2 and 4 6 3/4 6-19 thru 3/4 6-21. M).a.
A.2)tL12 A2)A1A3 None.
3/48.3 3 4 3a. 3 4 30. and 4.7 - 3/4 6-22 thru 3/4 6-24
. A.2).a A2)tL1.2A4 A.2)A None.
3/464 3.3 3. B3.3.3. 4 4 A and 3/4 6-26 thru 3/4 6-26._ A.2).a A2)tL1 None None.
Tatue 4.2-1 Rom 8.
3/4.6.6 8416, Tatde 3 5-6 hem 3/4 6-27 thru 3/4 6-29.- M).e.
M)b 1 A3 A2) c.
None.
- 12. Tetse 41-1 hem l
37, and Tetse 4.18-1 Rem 11.
3/4.66 346.42.2. end TatWe 3/4 6-30 thru 3/4 6-31., A.2).a.
A.2).D. _
A.2) c.
None.
416-1 nom 9 l
S/4.7.1.1.
3 61s. 93 6. Tatdo 4.1-2 3/4 7-1 tvu 3/4 7-3 M).a.
A2)b 1.2.
A2) c.1.2 None-Rem 7.
j l
.i-ad
1 s
Federal Register / Vol, 55, No. 94 / Tuesday, May 15, 1990 / Notices 20221 TABLE I.-CATEGOR11AT10N OF CHANGES TO THE CURREwt TECH. SPECS.--Continue
=
l
~
Categwy Normeeon from Nf# dor roweed sectvuceb--J Z -e a_n9ee.e.e.t are
_De6eson_s from._Sie P
Ch W toch spec Wel AdrreustratNo Asdood 2 spec No.
NSH s_ppe_ ruts A page e
e
_9ee 3/47.12_
814,4.10,M6s 416-1
- 3/4 7 4 fru 3/4 74 - M).e M).b.-
A.2)4 None.
3/47.1.3
_319. 83 it, and 422 3/4 7-7 9eu 3/4 7-8 A2).a Nore A2A None.
eam 3.
3M_
3/4 74 evu 3/4 7-10 A2).a.
A.2)h12,3 None None.
3/4 7.1.8 --
381.b. 3.8 it 3 8.3, 3/4 7-11 etu 3/4 7 A.2)4 -
A2)tt12 A2)4 None.
3/47.14..
3/47.1.8.
3.20,421,83J0, and 3/4 7-13 9vu 3/4 T 1e MJ.a A.2)JL None-Nor9 4.0. and 84.0 3/4 7J _
8 4.4. 83 4 4. and Tab 6e 3/4 7-15 9vu 3/4 7-10 A 3.4
- M)b.113 A.2).c 1,214 - Nors 8421.
3 4 5, B3 4.5. and Teb6e 3/4 7-19 tvu t/4 7 A2).4 M)b 1,2__ A.2)4113.4 -.
- 4cne.
416-1 nem 4.
3/4.7J.
3/4.7 4 _ _
Nore. Adde New 3/4 7-23 vvu 3/4 7-24 A.2).e None _
4.16-1 hem 7.
i 3 4.7,4 7.3, and 84.7 3/4 7-25 #wu 3/4 7-27 M)4 A2).b.113.4 M)t1.
None.
SpecAccoon.
3/4 7.0__
3.13 erd 4.14 3/4 7 28 fru 3/4 7-29. A2) e A2).b.
None _.
None.
3/4.7J 3/4.7.7..
311,4.12 and B3.11 3/4 7-30 thru 3/4 7-32 A2).a A.2)tti,2___
M)* _
None.
3
^
3/47.01 3142 and 415.2 3/4 743 thru 3/4 745-A2),a A.2)b.113 M)ti,2 -
None.
3/4742 314 3 and 415 3 3/4 7-36 thru 3/4 7-39. AJte A.2)b 113 A.2)*12 Nonet
[
3/47.8.3 314 4 and 414 4 3/4 7-40 thru 3/4 7-42.. A.2).e None A.2)b 1.2
- None.
3/4784 Hone. Adde New 314 7-43 thru 3/4 7 A2)4 None _.
M)tNone
-. None.
+
3/487.9 3.14.5 and 4.15.5 3/4 7 45 evu 3/4 7-47. M) e A2) b 1 M) c.12 None.
l Specmceeon.
3/4811-3 7. 4 6.1, B3 7, B4 4.
3/4 6-1 evu 3/4 6-0._ A.2)41 A2)tt1J14.
A2)*113 Nonet A.2).b.5.6.7.8 -. A2).c 4,5,6,7_..
Table 4 6-1. Table M)D.O.10,11.12 41-2 nem 12 and 3/4 81J None. Adds New 3/4 6-10..
A.2).e None None None.
Tebie 416-1 Item 5.
i 3/4821 5.7,4 4 2. B3.7, and 3/411-6 thru 3/4 6-14 A.2).e M)b.1.2,3_.-. A2)41.2 None.
Specrhca:m 3/4 SJ.2 kone. Adde New 3/4 6-15 M) a None None.- _
None.
S4.8 3/44.3.1 3 7. B3 7. Table 4.16-1 3/4 bi6 thru 3/4 6 A.2).e -
A.2)b.1214.5.4.- A2)t1 -
None.
$pecmceeon.
3/48.3.2 None, Adde New 3/4 bi9 A2).a None None None.
Item 10.
3/491 310 8. 8310.8. and 3/4 01 thru 3/4 9-2._. A.2).e A2)b 1,2 A2)r None.
Spec 6cesort 3/491 310.3. 9310 3. rnd 3/4 94 thru 3/4 9-4_.. M).s M)tti,2 -
Tebe 41 2 hem 13 b
3.10 5 and 8310 5 3/4 9-5 thru 3/4 6 A2).a A2)tx __
None NoneL Table 41-1 hem 3.
3/404 310.1 and B3101 -
3/4 9-7 thru 3/4 94 A2)a A2)D. __
1/493 3/496 310 6 and B3 to 6 3/4 9-9 tvu 3/4 9-10..... A2).a A.2)b.
None.---
None.
3/4.98.
Table 4.1-2 nem 9 -
3/4 9-11 thru 3/4 9-12 A.2).e A2A113.4.5_. A2)t Nonet 3/4.9 7..
310 9 and B310 9 3/4 6-13 thru 3/4 6-14.-. M)4 A2)tt None Nonet 3/49.81 310.7.1, B3.10 7. Table 3/4 bt5 thru 3/4 6-17 A.2) e A2)tk.
A2)*
Nonet 41-1 tem 13. and 3/498.2 3.10 7.2, B310 7. and 1/4 9-16 thru 3/4 6-20.. M) e A2)b.
A2)*
None.
Tabte 41-2 som 18 3/499.
310 2. 8310.2. and 3/4 021 thru 3/4 b22.
A.2).a A2)b.
Table 41-2 Rom 16 None. Adds New 3/4 9-23 thru 3/4 b24
, A.2)4 A2)tt _
None.
None.
Tebie 4.12 mem 8
$/4.910 3/4911 None. Adde New 3/4 9-25 thru 3/4 b26. A2).e __ -
4)tk None.
Nonet Specacetm 3/4912 312,9312, Table 4.1-2 3/4 b27 avu 3/4 b28 M).s A2)b.
None.
None.
Spececaeon.
3/4 9-29 trvu 3/4 6 30.~.I A2)4 A2)b.1.2 None-Nmne.
nem 17.
3/4913 3 to 4. 8310 4. and 3/4914 317. B317, Tebie 41-2 3/4 9-31 thru 3/4 6-32 M)e A.2)b.
None Nonet Table 41-1 nem 16A 3/4 to 1 3.21r
_ _ 3/410-1 ery 3/410-2.. A214 A.2)tx None.
None.
hem 13 3/4.10.2 3 216. 3 2 tb. 3.2.1C.
3/410-3 trvu 3/410-4.. A2)4 A2)tr None.
None.
3/4103 31.21,3 2.1.e. 3.21.b, 3/410-5 tvu 3/4104.. A2)4 A2)b.
3 2 6 6. and 3.2 6 ft 3/4105 None, Adde New 3/410-7 thru 3/410-8.. A.214 A2)b. -
None.
None.
3.214 3/41111.
3 9 to. 83 01a. and 3/411-1 tvu 3/411-2. A2).e..
A.2)b None.. __
None.
Spececebort 3/4111.2.
3 91 b. 6 9 3e. and 3/411-3 thru 3/411-4.. A.2) e None None None.
Table 3 S-1, d 3 91 d. B3 91.c. and 3/411 5 thru 3/411-4..~ A.2).e None..
None.
. None.
B3 91 b
[
3ie 11 1.3 -.
l 69.3I.
-,=-w-.--.m
.. ":-~~~
202 2 Federal Rigister / Vol 65, No. 94 / Tuesday, May 15, 1990 / Notlets p
TAst.E 1.--CATE00Rt1ATION OF CHANGES TO THE CURRENT TECH. SPECS --C a
- i Cenegory W4onneton kom NSH lor sensed techngel W W tem spec. No, M M epec. M g p a.epg,d,g peg, Agp n gq,gg,,
4 p
OleLehe.t ar e Doiosons born p
- ee
- e. - tem e a l
S/4.1111
. 3 0.2a. 83S.24. and 3/4117 thru 3/4118. A2).e None None None.
Tente 3.6 3.
3/4.11.2.2-4-
3.82D. 83AJb. end 3/4110 9tu t/411-10 M).e None A23tL None.
822s.
4 6/4.11 2.3 3AJ.A 33.8J.4 eid 3/411 11 gru 8/411 A.tka 9tme None _
Nont SAAe.
12.
8/4.1114 3 9.2e. 8332e. and 3/411 13 tus 3/411 M).e None None None.
49Je 14.
S/4.112.5 3 9.2 p. B192. Tat 4e 3/411 18 gru 3/4 n.
A *).e Nme None None.
3 3.64 IL 8/4.1116 3 911 and B3 Dif 3/41117 #wu 3/4 *1 M).e M)D.
None _ --
None.
1E S/4.11 3 3.8.3 and 53 0.3.,-
3/411 19 Ovu 3/411 A2).e A22. _
1eone
. None, i
30.
3/4.11 4 i
3 9.2A. 83.02A eruf 3/41121 tvu 3/411 A.2)J A.2)D. --
8.8AA 22.
S/4.12.1-Att 1. D4.12.1 and 3/4121 M).e -
None None-Nont SA 3L S/4.12.2 412.2 and Bd.12J 3/4122-A2).e None teore Nont 3/4 12.3 412.3 and D4.12.3 3/412 3 Wyu 3/418 4
. A2) e None _
6.1
. 6 1 -
-- ~
Sit _-
3/4 51 Wou 3/4 6 A.2Le A.7)tt M)c Nons and page 4 None. Adde New Doogn 6-4 M).e tenne Nous-None.
Feature.
622.-
6JA2_
6-6 peu S-4 Mie Mk None
. Deone.
6.31 52.1 6-7 tvu 6-4 Mle None None penne S32-625 6-0 thru 6 M).e -__ None None None.
S 4.1 --
None. Adde New Desse 611 stu 612-M).e None None None.
Feature.
84.2
. 613 i
None. Adds New Deegn_
6-13 evu 614 Mte None None None.
5 5 --
bi6 svu bl6 A2ke.
None None None.
Feature..
t 68.1-6 4.2 and 5 4.3 517 pru 5-18 A.2Le M)tL1.2 None.
None.
>j 8SJ None. Aods New Desgn S.te tvu5-20 A2).e -
None,
Nons None.
Feature.
S 6.3 -
No% Adds New Design 6-21 tvu 6 22 A.2).e None None None.
Feense.
6.7 -
None. Adds New Design 6-23 vvu 5-24 M).e --- None _
Feehre.
8.1_
6.1.1.-
61 thru 6-2 611 82.1
. A2M A2)tk None None.
6 3 thrv 6-4,
. A.2Le None None None.
l 8.2.2 622 -
b5 pru 6+ %
M).e M).b None _ _. None.
$13 811 b7 eru 6 8 A2ke None None
- None, c
6.3._
S.3 b9 thru 610 _
A.254 A2)tt adone None.
84 64 611 vvu 8-12 A.2ke A2)tk peone Nont 411 611 613 thru 6-15 Mke._
A2)tL113 A2)c.1,
Nont 662
&51 6-16 tvu 6-17 M ke None _
Mitt None.
&5.3 None, Aels New 6-14 tyd 6 19 None M).e A2)4 None.
Spoohcabort 66-68 6-20 evu 6 21 M).e None None None.
8.7 --
8J S-22 Wou 6-25 A21e A2)tL2 A22.1 erms None.
88-6 8. 613. $14. s.15, and 6-2s Fru 6-28 A2Le A.2)b.12 M)e Mont M)c.1A 6.16.
49.1 6.9. 6 A 1. CA3, and 6-29 Svu 6 32 A2).e A2)tL1,2
%me None.
8.94.
632 491a.80.3.D,and 6 33 puu 6 44 Mie None -
None _ _ _ Nme.
6 9 Ac.
4 10 6 10 6 36 thru ba6 A2La _
A2)tL1,2 None None.
Li t.., -
8 11 6-37 uvu 6-30 A.2).e _ _ None Mone None.
412 -._
_612 6 39 vvu S.41 A2La A2)D.1,2 M)b.3
- None, i
413 - _
8.17 6 42pru643 M)4_
M)tt Dione None.
4 14 6.10._
6-44 evu bd6 Mke tegne None None.
s.16 None. Adds New 6 46 Nru 6 47 None-M).e None Nont Speclecesort None 34.1(2 _
G 1 tvu 0.4
_None None.
one bem __. 34.1.e.2.
None Tabte4.11 G 1 gru G.4 None None seven terre Tet4e 4 tot beeis.
12.13,14.16.10 None _
Tobis 4.12 G 1 thru G-4
. _ None _ _ _._ None tour home
_ Table 4.12 home 4 24, 25.
None 4.18 -
G 1 evu G.4 None None onelusn 4 18 apower 9.15. and 1&
I eveitetwery "
~
ym
Federal Register / Vol. ST) No. 94 / Tuesday, May 15, 1990 / Notices 20223 TAst.E i.-CATEGontIAttoN or CHANGES TO THE CURRENT TECH. SPECS.--Continued Cawgory rdormahon from NSH for revteed technscat opeufcatone Rowined tem spec. No CW'ent toch spec No(s)
NSM appenda A page Aewustratrve M C**P8 that are Deeetions from the references chang.:
4"C'"'
Cham.
r oons went tech spec.
None Secton 5 Dewen G-1 erv G-4 None None
..... Wewen hems.... 6.2 ta & 2b. 6.3 A 1 Featwos 6 3.A 2. 6.3 Bt &
B2. 6 3 C 1.
b 3 C.2. 6 3 C 3.
6 4 t. and 6.2 4 The Commission provides bases for a Category 1-Administrativa Changes generalized statement of applicability, a proposed no significant hazards consideration determination in 10 CPR Examples of administrative changes statement of purpose of the TS, and a include consolidation c,f requirements in detailed specification which combines 50.92.These include the three standards one piece. reformatting of requirements.
requirtments with actions to be taken if set forth in 10 CFR 50 92 for determinin8 numbering of all paFes. and revision of requirements are not met.The RTS have whether a significant hazards definitions (part 1 of the TS). Three an improved format which sets forth the consideration exists. Under the examples are discussed be;ow.
requirement stated as the Limiting Commission's regulations in 10 CFR Example 2: Consolidation Condition of Operation (LCO), the 50.92, a proposed amendment involves operational mode applicability, and the no significant hczards consideration if in the CTS. requirements for a Fiven statement of action required if the LCO operation of the facility in accordance plant system r component are often is not met. These requirements (LCO.
dispersed throuF out a number of h
with the proposed amendments would applicability, and action) are organized Snh ns fee S. The RTS not:(1) involve a significant incicase in as separate entities and presented in the the probability or consequences of an c no hdatn the requirements for a same sequence with a heading in capital accident previously evaluated, or (2) 8(([g'n h ch IIipIoves 8
create the possibihty of a new or R
different kind of accident from any organization. The changes in the accident previously evaluated, or (3)
Refueling Water Storage Tank Reformatting has not resulted in any involve a significant reduction in a requirements are an example of thiw changes to the plant operating margin of safety-type of change.The CTS limits on requirements that are in the RTS. Since borated water volume and boron reformatting does not change any of the Before lasuance of the proposed license amendments, the Commission concentration are located on page 3.4-1 requirements contained in the TS, of the CTS in section 3.4.1.a.1. and the ref rmatting does not (1) involve a will have made findings required by the requirement for a weekly verification of significant increase in the probability or Atomic Energy Act of 1954, as amended boron concentration is found in Table c nsequences of an accident previously (the Act) and the Commission's 4.1-2, item 't (there is no page number:
evaluated; or (2) create the possibility of regulations.
the table is located six pages past page anew r different kind of accident from Esaluntion 4b1). In the RTS. this information is any accident previously evaluated. or (3) consolidated in one place in a Refueling inv lve a significant reduction in a The licensee performed a detailed Water Storage Tank TS on page 3/4 5-O 9' a
.a it a
evaluation of the changes proposed in 9, located in Section 3.5.4 Limiting the RTS against the above standards Conditions for Operation, and on the
[n fa' f a1 lud 8"
and concluded that none of the same page. Section 4.5 4. Surveillance preposed changes involves a significant Requirements.
that reformatting throu hout the RTS involves no si nificant azards hazards consideration.
Reference:
Because there is no technical change 8
Att6chment 11. Appendix A. of the related to consolidation, i.e., the considerations.
Application.
consolidated requirements remain the Example 3: Revision of Definitions The staff reviewed the No Significant same, consolidation does not (1) involve In its no significant hazards Hazards Evaluation (NSHE) provided in a significant increase in the probability evaluation (Appendix A of Attachment 1. Appendix A to the June 5.
or consequences of an accident 11 of the Application, pages 1-1 through 1989 license amendment proposal. Based previously evaluted, or (2) create the 1-3) the licensee evaluated changes in on that review, the staff agrees with the possibility of a new or different kind of part !(definitions) of the CTS and licensee's conclusions that the proposed accident from any accident previously concluded that no significant hazards amendments involve no significant evaluated; or (3) involve a significant consideration is involved. On page 1-1 hazards considerations.The staff has reduction in a margin of safety. The of Appendix A. In items 2.a. 2.b and 2.c selected examples of the proposed TS three standards of to CFR 50.92 are respect vely, the licensee notes that 11 changes in each of the four categories of satisfied and the staff concludes there is new definitions have been added, characterization (administra tive, more no significant hazards consideration.
refueling interval has been explicitly restrictive. etc.) employed by the The staff also concludes that-defined and 13 definitions have been licenree and which also cover the six throughout the RTS where consolidation deleted. Generally the added definitions part of the RTS, and they are discussed has been made, there are no significant are related to specific parameters which below. These examples are considered hazards considerations involved-the TS help to control, such as various to be typical of the proposed changes Exomp/e 2: Reformatting leakages. tests, and neutron flux.
The staffs evaluation of no significant in the CTS. beginning on page 3.1-1.
Examples of added definitions include hazards is presented below.
the format of the TS consists of a very pressure boundary leakage er:tuation c
I 20224 Federal Regist:r / Vol 55, No 94 / Tuesday, May 15,1990/ Notices logic test. and axial flux difference,The be of interest to persons outalde the unita, the combination of reactor
=
deleted defmitions, on the other hand, are general terms which are either not reactor operations field, the definition in pressure, temperature, and thermal needed for specific controls or are not the CTS ("those restrictions on reactor power level are not permitted to exceed needed because they already exist operetion, resulting from equipment certain hmits provided in Figure 2.1-1 performance capability. that must be (no page number). However, no explicit somewhere else f for example,in the enforced to ensure safe operation of the required action is identified in the Cn if
{
Code of Federal Regulations). Examples facihty")is obvious and unnecessary for the hmits are exceeded. Instead, the of deleted definitions include design power, safety lirnita, and reactor reactor operators and personnel ano operstors are referred to CTS Section NRC staff by whom the TS are used.
3.0.1 which requires that action be protectton system.
Furthermore. LCO is described in to initiated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to reduce reactor ne beensee has addressed the three criteria of to CFR 50.92(c and CFR 50.36. An example where a deleted power and place the reactor in a determined that they are) satisfied dermition has its useful content different appropriate operating moda, because:
transferred to a specific TS is " Safety the earliest being Hot Standby Limits". In the CTS on page 1 1, the (operational mode 3) within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
L tt)ne propowd change as descrbd in Item La 6e atenitar to example (il of es nt definition states that if any safety hmit However, in the RW Section 2.1 (page 1
is exceeded, the reactor shau be ahnt 144?0 in that it is an aduunistret to change down until the AEC (now the NRC) 2-1). the same hmits apply, but a which consobdates current requirements mto specific expucit actico statement has a technical spserfication farmat consistent authorizes resumption of operation. This been added. This follows the format of statement refers tp action required the !TTS. The action statement is more n does n in 1e rather than stating a definition. The restrictive because (1) it requires the or modificauona action to shut down has been operators to place the reactor in Hot (2) he change in Item 2.b is similar to transferred to the individual RTS Standby within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> instead of 6 eumple (ii) of ea m 14s'o in that it pewides Section for aafely limits in Part 2. The hours, and (2)it refers the operator to addmonal r,.tncemns and controis by action to remain shutdown until NRC Section 63.1 (page 6-12) of the RTS, requirty surveillances with frequmq R to be performed et lent once pw is meth*-
approval is obtained to teatart is which provides reporting requirements.
(3) The proposed changes descibed in item transferred to page 6-13 of the RTS in Also, C'm Section 2.1 requires that Section BJ.1.d. The remainder of the et se or h cF a e ed in et pi ca
" Safety Limits" definition in the CTS is specified power / pressure / temperature in the revised technical specifications. In general in nature and la also described hmits for one-and two-loop operation some cases, the proposed changes described in 10 CFR 50.3e and natural circulation not be exceeded.
to item Ec represent restnctions to plam The revision of the definition of However. because these hmits have not derimuon contains a restricuan the refueling interval specifica a time been analyzed in the safety analysis, operation In each case where an omtrted they are being deleted.
restncuon is incJuded in another section of interval of to months or less. which in the Ucensee's no significant tb revised technical specifications-clarifies what is rneant by refueling bazards evaluation, Appendix A of s
d bierval. No specific time interval is miso aEe s$i er defined in the CTS so that a refueling AttachmentIIof the Application,pages in e e araple 48 R 1487o in that they are administrattve interval could be any convenient period 2-1 and 2-2, the licensee evaluated the cherres which coneohdate current of time resulting from an actual fuel changes to Section 2.1 of the CDin format consistemt with the standard cycle. He revisod definition brings the accordance with the three standasde of requirements into a technical specification lechnical SpecJhca tions and do not involve Turkey Point definition in line with STS 10 CFR 50.92(c) and concluded that the changes do not involve a significant technical or plant modifgations.
practice in the industry. No significant hazards consideration. The NRC staff increase in probability or consequences
)
The staff agrees with the licensee's of an accident. creation of a new or agrees with the licensee's determination conclusion that there are no significant different kind of accident, or reduction and adds the comments below regarding T
hazards considerat:ons. with the in a margin of safety can result from the three standards of to CPR 50.92(c).
following additional c:omments. ne these changes because the revised Operation of Turkey Point Units 3 and changen in defintoons described on definition is narrower, and is thus 4 in accordance with the propa*.ed changes described above would not:
pages 1-1 through 1-3 of Appendix A to encompassed within the CTS definition. 1 of the Application do not (1) Involve a significant increase in (1) involve a significant increase in the Category 2-RNrequirements erhich the probabibty or consequences of an probability or consequences of an ore more restrictive or more complete accident previously evaluated. No accident previously evaluated. or than C73 requhements bcrease in accident probabihty will create the possibihty of a new or (2}
Examples of proposed changes in result form reducmg reactorpower
- different kind of accident from any requirements which are more restrictiva sooner when core limits are exceeded.
accident previously evaluated, or (3) or mon complete than those now in the because reducing power sooner will involved a significant reduction in a m are discussed below. These bring the reactor back to within the margin of safety because. (a) the added include: examples of changes to safety required hmits at an eather time. Also, defmitions help to clarify and avoid limits and limiting safety settings in Part restricting the reactor to thMoop mirinterpretation of existing terms 2 of the TS. example of changes to LCOs operation removes the possibilities for related to specific controls and taats.
in Part 3 of the TS. examples of changes thermal stresses and temperature and (b) those definitions deleted are to surveillance requirements in Part 4 of gradients associated with asymmettse either very general and therefore not the TS. and examples of changes to coolant flow which could accompany a
very useful. or they exist elsewhere, or administrative controle in Part e of the operation with only one or two coolant their useful content is included in the E
loops. In addition. since there is no specific relevant technical specification.
Example t Safety limits and limiting change in the design basis accidents. no For example, one deleted definition is safety settings increase in consequences is possibia.
Umnting Conditions for Operation In CTS Sections 1.1 (page 1-1) and 2.1 different kind of accident froaa any
- 12) Create the possiblitty of a new or (LCO). While the LCO definition might (page 2,.1-1) covering reactor core safety accident previously evaluated. Because l
L-- -.
Federal Register / Vol. 55. Ns. 94 / Tuesday. May 15. 1990 / Notices an22n the changes merely deal with reducing and mode applicabihty) are all as signtBeant basards consideratums The the roector power sooner to bring the restrictive, or more restrictive, than the staff has reviewed all of these changes reactor back within required limits.
CTS.
Individually and agress with the there is no new or different kind of Therefore, the staff concludes that the licensee's sanclueton.
accident created.The removal of three standards of to CrR 80.82(c) are Reporting requirements are alternative conditions of operation. such met, and that there an no significant considered to be typical of as two loop operation, does not create a hazards considerations. ne staff further administrative controls in that they do aew or different kind of accident concludes that, throngboat the RTS.
not have a strong imsnediate influence because no new operating conditions proposed changes consisting of on the probability of an accident or its are incorporated, additional or amore restrictive LCOs.
consequences (compared. for example.
(3) Involve a significant reduction in a action statements,and mode to the level of reacter pressure or margin of safety. The proposed changes applicability involve no mightficant temperature or the aveWebility of increase the scargin of safety by hazrds considerations.
cooling systemel, ce on the lond of requiring the reactor to reach Hot Example 3:Surveillances and tests accident or the margin of safety. A Standby sooner, by limiting the in the containment att temperature detailed example and analysis of the operation to three loops. and by example discussed above, no proposed changes follows:
providir.g clear guidance for timely surveillance or test requirements were in Sections 6.9. 8.916.9.3. and 6.9.4.
notification of authorities.
prcvided in the CTS. The proposed beginning on page M5 of the CTS.
The steff cor.cludes that the above changes in the RTS in Part 4 (page 3/4 & requirements are described for reporting changes do not involve a signiacant
- 7) add a surveillance requirement to various information items to the NRC.
hazards consideration.The staff further determins containment temperature at The RTS adds a new requirement for concludes thet, throughout the RTS.
various locations at least once every 24 reporting challenges to the PORVs or similar proposed changes involving hours. In Appendix A of Attachment !!
safety valves. In addition, the RTS safety limits and safety settings found of the Application, pages 3/4 64 and &
clarifies the reporting of changes in the primarily in Part 2, which are as
- 10. the licensee evaluated these changea analytical procedure for determining restrictive es. or more restrictive than, against the three standards of to CFR peaking factor limits.
the CTS. meet the standards of 10 CFR 50r(c), and reached the conclusion that These RTS changes do not Som(c) and do not ir volve significant no significant hazards considerations significantly increase the probability or hazards considerations.
are involved.The staff agrees with the consequences of an accident previously Exomple 2:LCOs licensee's conclusion and offers the evaluated because reporting The CTS provided no requirements for following comments. Adding new requirements are only indirectly linked containment air temperature. The surveillance requirements or increasing to accident probability. Adding changes proposed in Section 3/4.6.1.5 of the frequency of existing surveillances reporting requirements in the RTS does the RTS (paSe 3/4 6-7) include new for equipment that is important to safe not significantly increase acr.ident or P ant operation can provide additional consequence probability, does not l
limits on containment air temperature.
an action statement that requires reactor knowledge of the plant status so that create a new or different kind of power reduction if the limits are operators can take timely corrective accident. and does not reduce safety exceeded for a stated time interval, and action if needed. Therefore, this helps to margins. Reporting requirements alert stated operational mode applicability reduce the probability or consequences the NRC to the status of plant (modes 1 through 4) that orplies the of an accident. Such action also helps to operational activities of the licensee and LCO and action statement to those prevent new or different kinds of provide generic information for use in operating moder, in which a serious accidents from occurring. and helps to long-term investigation programa.
accident is most likely to occur (at maintain desired margins of safety.
Likewise, the clarification of The staff concludes that the three requirements simply removes some of power or while the reactor is hot).
in Appendix A of Attachment 11 of the standards of 10 CFR 50.92(c) are met-the latitude for interpretation previously Application, pages 3/4 6-9 and 6-10, the and there are no significant hazards available to the licensee.
licensee evaluated these additional and considerations involved.The staff also The three standards of to CFR 80.92(c) more hmiting requirements against the concludes that throughout the RTS.
are met for these changes, and the staff three standards of to CFR 50.92(c)-- and where surveillance or tests have been concludes that there are no significant concluded that the proposed changes do added or made more extensive or hazards considerations.
not involve significant hazards fmquent, there are no signihcant considerations The staff 6grees with the hazards consideration involved.
Category 3.-Relarah,on of CTS licensee's conclusion and adds the Example de Administrative controls Requirements following comments. Because additional Changes proposed in Part 6 of the RTS Throughout Appendix A of and more limiting requirements are include changes in requirements for 1 of the Application, the imposed on plant operation, the reporting, qualifications for operatora, licensee has identified a number of probability of an accident and its procedures. training scope, programs changes characterized as " relaxations" consequences are reduced it is less (e.g. chemistry). records retention, high from the CTS. The NRC staff review has likely that the containment and the radiation areas, review and oversight by determined there are no cases where a equipment in it will fail or cause an review committees, and NRC approval significant relaxation has been made accident due to high temperatures. Thus, of the Process Control Program. AB of and not identified as such,in a few there would be no increase in these changes are evaluated by the cases the staff does not agree there is a probability or consequences of an licensee in pages 6-1 through tk 47 of relaxation, but because the licensee's accident.There will be no new or Appendix A of Attachment 11of the characterization la conservativa, it is an different kind of accident created, nor Application. The licensee has evaluated acceptable characterization. Nearly all any reduction in a margin of safety these types of chariges against the three of the licensee's proposed relaxetions because the added requirements standards of to CFR 50.92(c) and are in Parts 3 and 4 (LCOs and (addition of an LCO action statement.
concluded they do not involve surveillance requirements) of the RTS.
l
.. _ _ _. - - - -. ~ ~,
~
mp 7
20226 Rd2rd Registir / Vol. 55 No. 94 / Tuesday, May 15, 1990 / Notices Only one relaxation was proposed in quadrant ower tilt ratio once per 12 Part 2 (safety limits), on page 2-5 of hours.Th licensee also proposes to surveillance, the alti dey survei!!ance to Appendix A of Attachment 11of the relax the surveillance frequency for rod other rod position surveillance requirements verify rod OPERABILITY. combined with e-Applicatioru the staff does not agree it is operability from 14 days in the CTS to 31 will adequately verify rod OPE a relaxation. Furthermore, the staff found no relaxations in Pat'1 days in the RTS.
- b. Create the ossibility of a new or The licensee determined that the three dmennt und o accident from any l
There were)4 relaxations pro osed in(definitions or Part 5 (design features).
standards of to CFR 50.92(c) have been
[ha rohu [no fp$nt Part 6 (administrative contro :): thee thet and there are no significant hazards w
are described in Appendix A of considerations. The licensee's operation norinvolves a physical 1of the Application on evaluation relevant to the requirements modines%n to plent.
Page M3, item A.2.c. page th23, items ofitem (A)2.c discussed here is
- c. Invo% e e signnelant reduction in a re duced below:
margin of safety. As discussed in item 3a A.2.c.1 & A.2.c.2, and page &28, item A.2.c. These relaxations of he proposed change to relax the above, the 0.3% rucuvity limit is not e restriction bued on any safety analysis requirements in item 2.c above, does not anumption, the hi nux setpoint reduction is administrative controls are not involve a signficient hazards not nece8sary to compensate for any adverse significant because they are minor changes which have only a weak link to consideration because these changes do g,P' '
aj s s, I*
not; d
on a e
o erational safety, For example, the e anges proposed on page %23, items a: Involve a signficiant increase in the and the 31 day OPERABLE tod surveillance is A.2.c.1 & A.2.c.2 of Appendix A of probability of or consequences of an accident consistent with industry practice and the 1 of the Application relax previously evaluated.
Standard Technical Specifications.
The reactivity limit in the current TS is not Based on the above considerations. the the time limit permitted for some needed to preserve any rod election analysis changes included in the development of reportin requirements.
design assumption. Other restrictions in the proposed Technical Specifications 3/tt.3.1 There re, the only relaxations of any proposed TS for MOVABLE COffrROL are considered not to involve a significant significance are in Parts 3 and 4.
ASSEMBLIES ensure that the normal rod hazards consideration as definad in to CFR 50.92.
Examples of proposed relaxations which $$y"pr'ese thio' n I afh" The etaff agrees with the licensee's are typical of those in Part 3 (LCOs) and Part 4 (surveillance requirements) and analysis limiting assumptione related to rod evaluation and conclusion and adds the the evaluation of no significant hazards position.
The current Technical Specince:lon following comments, in part a. there is a considerations are discussed below, nquirement to reduce the hi flux trip setpoint typog hical error in that the rod Exomple 1 Relaxation of LCOs and when both the rod deviation and the power opera ity surveillance test frequency is surveillance frequencies
[,'"yp';'
referred to four times as 30 days instead 8
$ r f que $
ib'n of the correct value of 31 days. This in MS sections 3.2.4. & b and 3.2.5.
d pages 3.2-2 and 3.2-3, requirements on The rod posluon surveillar.ce is increased example involves deleting an LCO that
~
from once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> movable control rods are stated. These when the rod deviation alarm is inoperable.
is not needed to preserve any safety include: a limit of 0.3% potential in the quadrant power title Technical analysis assumption. Where this type of reactivityinsertion by ejection of an Specification the power tilt surveillance is change occurs in the RTS, the staff inoperable rod, and a reduction of the increased from once per 7 days to once per 12 concludes that there are no significant high flux trip setpoint limit when alarms hours when the power range deviation alenn hazards considerations.The for both rod deviation and power range N.;$adequ comp nslte restrictive surveillances to accomplish replacement of an LCO with more E'
channel deviation are inoperable. lf either of these two alarms are INOPERABLE rod position deviation of the objective of monitoring plant status inoperable, the CTS action requires that power range channel devication alarm and while reducing the risk of accident from are consistent with industry practice in that control rod positions be lo ed once per these are the same SURVEILLANCE an unnecessary plant transient is also shift.The licensee has eva usted a REQUIREMENTS as in the Standard
' involved. Where this type of change proposed relaxation of the above Technical Specifications.
occurs in the RTS, the staff determined requirements in Appendix A of Relaxing the rod OPERABILITY test that there are no significant hazards 1of the Application,pages I
considerations. This change also 3/41-33, items A.2.c.1.2.3, and 4. and on ofonNir a si bifi cause of inv lves replacing an action whichis pages 3/41-34,35, and 36. The first the insign!!icant number of control rod drive not very useful(legging control rod failures determined by the current bl. weekly position) with one which addresses the (0.3%) LCO is relaxed in the RTS by deleting the requirement. The setpoint surveillance test.The proposed surveillance safety concern (power distribution) and reduction will also ahve the benefit of reduction LCO la relaxed by replacing decreasing the likelihood of inadvertently which is explicit with its own the requirement for a setpoint limit dropping a rod during the test and reducin8 subsection, " ACTION:". Throughout the reduction with two requirements which
""'jj"an
' lop RTS where this type of change in action increase the surveillance of the two statement is made, the staff concludes t
p Dd est surveillance frequency is increased from practice in that s[1] days is the Standard.
there are no significant hazards parameters.The rod position intervalls also consistent with industry considerations because the improved once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Technical Specifications surveillance knowledge of plant status that results interval.
\\
when the rod deviation alarm is from the change does not:(1) Involve a In summary, the proposed relaxations of inoperable, and the quadrant power tilt current Technical Specification requirements significant increase in the probability or surveillance frequency is increased from do not significantly increase the probability consequences of an accident previously once per 7 days to once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of r consequence 8 of a previously evaluated evaluated; or (2) create the possibility of when the ower range deviation alarm accident because: The 0.3% reactivity limit le a new or different kind of accident from is inopera le. The CTS action is relaxed "a j's s"r arg,e tpo$n$ Nu tio inv Ive a significant reduction in a any accident previously evaluated; or(3) in the RTS by replacing the logging of n y a now as rod positions once per shift with the appropriate a requirement to compensate for margin of safety, en INOPERABLE rod position deviation and more useful action of calculating the flux deviation alarm as the increased The staff also notes that this is an example where the surveillance fj C#
w'4W
~"
me Federal Register / Vol. 55, No. 94 / Tuesday, May 15,1spo / Notices
?st27 t
frequency is not critical to safety The staff agrees with the licensee's Colegory 4-4telocodien e/mquimmonds because of the low rate of equipment evaluation and conclualone and adds to amaraantrolleddocumeek L
Isilures, and where the test itself adds to the following comments for clarification.
The only example of relocation of the risk of fallare. Therefore, the staff This change is proposed because it is requirements from the CD to another concludes that, throughout the RTS, -
safer to shut down the two Tarkey Point controlled document is described en there are no significant hasards unite sequentially, rather than -
hage G-1 of Appendix A of Attankmani considerations associated with relaxing simultaneously, from the control room of b Appucauon.Dealgn surveillance freqeencies of this type.
that is common to both units. Because it requirements invo seven technical Example 2 Relaxed action statement takes about 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for one Turkey Point areas are proposed to deleted from within LCO unit to reach Hot Standby from full the CTS. The licensee has evelaated Section SSJ(pages 35-1 and 2) of the power in an orderly process.12 houre is these deletions against the three critaria CTS requires that four d.c. betteries be needed for two units to reach Hot of 10 CFR 80.92(c) page G-4 of Appendix maintained in an operable condition.
Standby.The added orderliness of A.no staff agrees with the licensee's ne action required,if one battery is control room activities and reduced evaluation.The staff notas that the inoperable for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,is to transient demand on plant equipment design requirements to be deleted from -
place both reactor units in Hot Standby obtained by shutting down only one unit the CTS are contained in another (mode 3) within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.The proposed at a time is safer than shutting down controlled document, the Final Safety change in Section 3.s.2.1 of the RTS both Turkey Point units simultaneously.
Analysis Report (FSAR). For example, identifies the specific four batteries, and While this change represents a relaxed the first design feature listed on page G-extends the time available to be in Hot requirement on the licensea, the staff 1 of Appendix A of Attachment 11of the Standby to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. In Appendix A of believes it is safer for Turkey Point.
Application. " Reactor Coolant System AttachmentIIof the Application,pages Also, specific identification of the design and maximum potential seismic 3/4 bit through 3/4 6-14, the licensee batteries is a desired clarification.
accelerations (section 5.2.2 a & b),"la l
three sten a o 10 C Exomple 3: Relaxation of surveillance located on page 5.2-1 of the C'!1 and a d 2.1 the
[
concluded there are no significant la the CTS, Table 4.1-1, item 1aB (no a gaQSm hazards considerations.The relevant page number, but follows page 4.1-1)
RTS.The othar six design features are part of the licensee's evaluation is area radiation monitors are required to
&scrbd cepletely in b FSAR.
reproduced below, be checked daily, tested monthly, and These design requirements are not used The proposed change to relax the action calibrated annually.The proposed by nactor operators. For example, b utrements to allow for a sequential unit change in the RTS would delete this as a design feMure chd above (section 5.3.2 sh tdown if a bettery is inoperable does not TS requirement.
a & b of the CTS) states the horiscatal involve a significent harerde consideration In Appendix A of AttachmentII of the and vertical seismic accelerotion halts
- "',' I,',*,Y,8'r*. fi t 1 ee in the Application, page 3/4 3-10. Item A.2.c.L for which the plant structures and d
ji y 3i c probabihty of or conse:;uences of an accident and on pages 3/4 3-11 through 3/4 3-13, equipment are designed.There are no previously evaluated. The proposed action the licensee evaluated this change relevant operating procedurse or statement requires within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ofloss of against the three standards of to CFR operating requirements dealing with a bettery that one of the effected units be 50.92(c) and determined there is no these seismic accelerations.The
{sced in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> significant hazards consideration accelerations were used to determine ehu o et' un\\ts associated with the change.The staff necessa structural strength when the I
H Yw
, s I
hours. Both units are required to be placed in agrees with the licensee's evaluation plant an equipment were designed and I
cot.D SHVII)OWN within so hours and conclusion. The staff notes that:(1) built. Because these design requirements following achimmat of HOT STANDBY.
These monitors are not used for are not used by the operators in their
. The preposed ACTION statement provides automatic protection during accidents, day-to day operation of the plant. the for a more organized method for a dual unit (2) other radiation monitors provide relocation of this materialis not a Indication of an accident by monitoring relaxation of requirements. A similar shutdown..
reps atton t me o hu7do I!he high radiation in the containment comment applies to all seven design second unit or restore the inoperable DC bus building, reactor coolant, or other requirements being relocated to the mo to operet.le status, and as the likelibood of an process systema, (3) these monitors wg]
FSAR.The FSAR is a bettar place to cecident being initiated during this additional be maintained and monitored using locate such information. Because there short time is remote, this change would not plant procedures, and they are backed is no change to the plant or its design involve e significant incresee m the up by area radiation surveys, and (4) operating requirements, the relocation of the seven design requirements does not:
probabihty of our consequences of as tMe change b conshted with h STS.
(1) Involve a significant increase in the accident previously evaluated.
(b) Create the possibility of a new or The staff concluoes that ehmination of probability or consequences of an differont kind of accident from any surveillances of this type,i.e., those not accident previously evaluated; or (2) previously onelysed because the eed required to protect the public health and create the ossibility of a new or fp ", C o,$ 'or"i ",5 p"hyNcl{ "i safety, involve no significant hazards different kind of accident from any d
considerations because they do not (1) accident previously evaluated, or (3) modificatione to the e nt.
(clinvolve e syni cent reduction in a involve a sign!Ilcant lacrease in the involve a significant reduction in a margin of selety because the revbion allows probability or consequences of an margin of sal'ety The three criteria of10 time to recover the DC bus while shutting accident previously evaluated; or (2)
CFR 50.92 are met. and there are no down one unit and prepartne for an organized create the possibility of a new or significant hazards considerations.
shutdown of the other unit. FP1. believes the different kind of accident from any Conclusion advantages of these operational accident prevloinsly evaluated; or (3) 8" erUtYet duel o involve a significant reduction in a Based on the above considerations, a ety kely shutdown le required.
anargin of safety.
the Commission has made a proposed
30228 Fediral Regleter / Vol. S5, No. 94 / Tu:aday, May 15, 1990 / Notic:s determination that the amendment of Consideration ofIssuance of this The amendment would incorporate
=
request involves no significant hazards considerations.
amendment was not published in the three proposed changes to the Technical Federal Register.
p gge -g, The purpose of the licensee's Specifications.The first proposed r
change would permit continued plant he Commission is seeking public amendment request was to eliminate the operation with two of the eleven Safety /
l comments on this proposed augmented ISI program being applied to Relief Valves (SRVs) out of service determination. Any comments received the main steam and feedwater piping (currently only one SRV out of service is within 30 days after the date of from Technical Specifications (TS) permissible for thirty days). This change publication of this notice will be Section 4.6J.2.
would also reduce the number of conalderedin making the final ne NRC staff has concluded that the automatic depressurisation system determination.
licensee's request cannot be granted.
[ ADS) valves required to be operable to Written comments may be. submitted The licensee was notified of the by mall to the Regulatory Publications Commission's denial of the proposed five of the seven valves (currently only one ADS valve out of service is Branch, Division of Freedom of change by letter dated, permissable for thirty days). The second information and Publications Services, By June 14.1990, the licensee may proposed change would replace the Office of Administration, U.S. Nuclear demand a hearing with respect to the staggered setpoints of the SRVs with a Regulatory Commission. Washington, denial described above. Any person single nominal setpoint.The third DC 20555, and should cite the whose interest may be affected by this proposed change would increase the publication date and page number of proceeding may file a written petition maximum setpoint tolerance for the this Federal Register notice. Written forleave to intervene.
SRVs from one percent to three percent.
comments may also be delivered to A request for hearing or petition for The associated Bases sections would Room P-223, Phillipe Building. 7920 leave to intervene must be filed with the also be revised to reflect these changes.
Norfolk Avenue,Bethesda, Maryland, Secretary of the Commission, U.S.
Other miscellaneous proposed from E30 a.m. to 4:15 p.m. Copies of Nuclear Regulatory Comminion, changes would clarify terminology, written comments received may be Washington, DC 20555, Attention:
correct typographical errors, delete a examined at the NRC Public Document Docketing and Service Branch, or may requirement to perform ADS logic Room, the Gelman Building. 2120 L be delievered to the Commission's functional tests which were Street NW., Washington. DC, Public Document Room, the Gelman inadvertently omitted from a previous For further details with respect to this Building. 2120 L Street NW.,
amendment application, and delete action, see the application for Washington, DC, by the above date.
Specification 4.6.E.4 which is redundant amendments dated lune 5,1989, as These documents are avialable for to a specification in section 6.9 of the supplemented November 3.1989 and public inspection at the Commission's Technical Specifications.
May 1,1990, which is avallable for Public Document Room, the Gelman Prior to issuance of the proposed public inspection at the Commission,s Building. 2120 L Steet, NW, Washington, license amendment, the Commission Public Document Room, the Gelman DC and at the State University of New will have made findings required by the York, Penfield Ubrary, Reference and Atomic Ene Act of1954, as amended
%a ston DC2055 at the Local Documents Department, Oswego, New (the Act)en the Commission's Public D 1
d et the York 13128. A copy ofitem (2) may be regulations.
r an t,
obtained upon request addressed to the By June 14,1990, the licensee may file Environ en a an
- Ubrary, Florida International U.S. Nuclear Regulator Commission, a request for a 1.eari with res$e ect to University, Miami, Florida 33199.
Washington. DC 20555, Attention:
lesuance of the amen ent to t Document Control Desk, subject facili operating license and Dated at Rockvills, Maryland, thia 9th day o Mayteen Dated at Rockville, Maryland, this 8th day any person w ose intemet may be i
For the Nuclear Regulatory Commieston.
of May 1900, affected by this proceeding and who Gordon E. Edlaon, Sr.
For the Nuclear Regulatory Commission wishes to participate as a partyin the i
Pmject Manager. Project Directomte 11-2, RM A.Capm.
Proceeding must file a written request i
Divison o/ Reactor Pro 'ects~1m. Officr ofDirector Project Dinctomte 1-1. Division of for a hearing and a petition for leave to l
intervene. Requests for a hearing and NuclearReactorRegu otion.
ejPm g;jmOffuofNuclear petitions for leave to intervene shall be es (F1t Doc. 90-112e1 Filed 5-14-em e-45 am]
l ouseo cosa ress.ews p Doc. 90-11265 Filed 5-14-em 845 am]
filed in accordance with the i
Commission's Rules of Practice for Domestic Ucensing Proceedings"in to g
g CFR part 2. Interested persons should Power Authority of the State of New consult a current copy of to CFR 2.714
(
Power Authority of the State of New York; Notice of Consideration of which is available at the Commission s York; Dental of Amendment to Facility Isauance of Amendment to Focility Public Document Room, the Gelman 0
ng Ucense and Opportunity for p
ng Ucense and Opportunity for Bu g 2120 L 8 g
DC 6hl
- Ihe U.S. Nuclear Regulatory Public Document Room located at the Commission the Commission) has -
The U.S. Nuclear Regulatory State University of New York. Penfield dInled a requ(est by the Power Authority Commission (the Commission)is Ubrary, Reference and Documenta consideringissuance of an amendment Department Oswego, New York 13128.
cf the State of New York (the licensee) to Facility Operating Ucense No. DRP-if a request for a hearing or petition for for an amendment of Facility Operating
- 59. Issued to the Power Authority of the leave to intervene is filed by the above Ucense No. DPR-59, lasued to the State of New York (the licensee), for date, the Commission or an Atomic i
licensee for operation of the lames A, operation of the James A.Fitzpatrick Safety and ucensing Board, designated i
FitzPatrick Nuclear Power Plant, located Nuclear Power Plant located in Oswegoby the Commission or by the Chairman in Oswego County,New York. A notice County, New York.
of the Atomic Safety and Ucensing
\\-
- - ^ - - -
-