ML18030B140
| ML18030B140 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 02/24/1986 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18030B135 | List: |
| References | |
| TAC-60870, TAC-60871, TAC-60872, NUDOCS 8603030299 | |
| Download: ML18030B140 (12) | |
Text
ENCLOSURE 1
PROPOSED TECHNICAL SPECIFICATION REVISIONS BROMNS FERRY NUCLEAR PLANT UNIT 1, 2, AND 3 (TVA BFNP TS 218) 8603030299 860224 P
PHOPOSEO CHMGES VNXT 1
lt
~
~
t 3 is t 1 1 iver.
Ci!)girl h~~v~~P 2 A~~ h'1 St1RV Kl'LANCE RKOJ t Rh~F?iTS 4.6.C Structural Ence"rf.tv 3.6.G Structural Inte rit a ~
tilth the structural integrity of any AS~K code Class 1
equivalent component, which is part of the primary system, not conforming to the above requirements, restore the
'tructural integrity of the affected component to within its limit or maintain the reactor coolant system in either a cold shutdown condi-tion or less than 50 F above the minimum temperature re-quired by NDT considerations, until each indication of a defect has been investigated and evaluated.
b.
With the structural integrity of any ASi~E Code Class 2 or 3 equivalent component not con-forming to the above require-
- ments, restore the structural integrity of the affected component to within its limit or isolate the affected component from all operable systems.
1.
The structural integrity of ASHE Code Class 1, 2, and 3 equivalent components shall be maintained in accordance with Specification 4.6.G throughout the life of the plant.
2.
lnservice in"pection of.~<~-
Coda Class 1, Cla 2,
and C3 "Qs 3 components G1lall be pc orated in accordance with Section ZX of the AZ 'oiler and Pres ur Vessel Code and applicable Addcnca as require'y 10 CFR 50, Sect'on 50.55a(g),
except where specific written relief has been granted by NRC purs~~ nt to 10 CPR 50, Sect an 50.55a(g) (6) (i).
Fcadvaoar CPU-9, Kjw-13 CP1-l2, C:~~-26, KFt1-31, CP:- c g,
~>-39, C-:-'-15,
'-38, and CPA-32 Adair iona 1 kn opoc "iona aha il bo
'orforead on certain c'-c cf cron-tial popo volda aa liaccd
".o pro-vide.dditional protcc".'on againac ptpo vhip, Mhlch could darwqo an"..iliary and control rya-tafQQ ~
<Incan otcaa C. lS-G, GHS 3
C]/S-1 5, k~8-24, GS-l04 and C~tS g 4 R11 R DSR/iR-4, DSR!.'q OSR1.>- SA 18 Cora Spray OSCAR 12, vS4S OSCS-5, aad
PROPOSED CHANGES VNXT 2
~Z 'sG CO aDZ 'O" S FOR OPERATION!
SURVE"LE.'4C= REOU"RE<~><T 3.6.G Structural ante rit a
0 Eolith the structural integrity of any AS<'EE code Class 1
equivalent component, which is part of the primary system, not conforming to the above requirements, restore the
'tructural integrity of the affected component to within its limit or maintain the reactor coolant system in either a cold shutdown condi-tion or less than 50 I'bove the mini...um temperature re-quired by NDT considerations, until each indication of a defect has been investigated and evaluated.
b.
'h'ith the structural integrity of any AS~IE Code Class 2 or 3 equivalent component not con-forming to the above require-
- ments, restore the structural integrity of the affected component to within its limit or isolate the affected component from all operable systems.
1.
The structural integrity of ASEEE Code Class 1, 2, and 3 equivalent components shall be maintained in accordance with Specification 4.6.G throughou-the life of the plant.
4.6.C St>>uctur"1 Entccricv 2..
-'novae iono ohcll p'cr fQ <<cd Qj ~
c gain cl <>n till pipe ucldn no lioccd>>0 pro v'dc cdi 'c al ion upaEnoe pipe vhip ~ vh'ch could 8>>ID4 ~c ollx <>
Pc odu= c c.
Cz <<'-9, CF4-1",
I"9-3>
KP>>-3'9, K~<<-38, YZv-13 GF '-Z5, Cc <<-i9, Cr v'-15, onc CP>>'-
- ~
<nservB.ca insnec>>'on op Coda Class 1, Cla s 2, and Class 3 components shall be par or ad in accordance Sec"'on Z o" the c." Bo'ler and Pressure 7essal Code and appl=cable Addenda as required by 10 C~ 50, Section 50.55a("-},
except where serac'"'c i"tan relic h"s been granted bv h~C pursuant to 10 KR 50,= Sect>>on 50.55a(g)(6)(i).
Hnin o(con CHS-6, ~S-E4, O'ES-32, Q.S-;04 nd Cu5-.2 Caro Szrcv TCS-407 TCS"423 TSCS-40S TSCS-424
PROPOSED CHANGES UNIT 3
tZHIT hG COJJDXTZGJJG FOR OPEr~'7ZO.J OU>VErp~r~rJOs Rr.pU YRr.-t 'JJ, S Jr~R
~
R S
W'~!.1 JJOI JJJ D iRY JJ ~ 6 PR7!1AELY SYST" H BOJJHDAJ(Y 3.6.0 Structural ante rity 1.
The structural integrity of ASlfE Code Class ir 2, and 3 equivalent components shall oe maintained in accordance with Specification
~~..6.G throughout the life of the plant.
trith the structural.integrity of
.ny AS LE code Class 1
equivalent component, which is part of the primary system, not conforming to the above requirements, restore the structural integrity of the affected component to within its limit or maintain the reactor coolant system in either a cold shutdown condi-0 tion or less than 50 F above the minimum temperature re-quired by ND'E considerations, until each indication of a defect has been investigated and evaluated.
G f3C~llccurll T.J 'ccz'icy l~
'"service msJJec" on o-Code Cl ss 1, Class 2,
Class 3
corn Qncnts sna1 l be Per"armed c
accord"nce -i"z Sec""'on W o t'"e K~~ Bo~ e" and -ress re Vessel Co"e ""d auolicab 4 e.~ddeqda as ec,.
'y 10 ~ 50, Sec""on 50.55a(g),
e.accept where s'hei i re3.xe" ras peon e~~v i rid by
%pC pu suant to 10 K3. 50, Sec"'cn 50.55a<:.) (6) <u.
h'ith the structural integrity of any ASiK Code Class 2 or 3
equivalent component not con-forming to the above require-
- ments, restore the structural integrity of the affected component to within its limit or isolate the affected component from all operable svstems
~
hddiCiora2,
~ rJspocCioJJS
. hall:3e performed o.. cerCa' circunforonCial p'pe do as l.s"od Co p"ovide addiC'onal pro Cec'C on a(ja nsC P" PQ
'c'JM.Pg i'Jhich oou'd dosage au:(ilia~ and conC o DrrrsComis o Pc dna or G?JJ-9,
!;";<-13 ~
Gr.".J-12~ Gi&l-26y NFaJ-31~
G.J'-29 Ei,Ã'J-39 g GPi J-i5~
RFiJ>>30, and G?H-32
~
~
Nl
r1 r.'NCLOSURE 2 Description and Justification Descri tion of Chan e
Replace the Limiting Condition for Operation (LCO) 3.6.G of BFN units 1, 2, and 3 technical specifications (TS), page numbers 183, 183, and 196 respectively, to expand applicability to include not only the primary coolant boundary but also the balance of ASME Code Class 1, 2, and 3 equivalent systems.
Reason for Chan e
This change is in response to an NRC request for additional specifications to clarify LCO 3.6.G.
Justification of Chan e
The regulations for inservice inspection (10 CFR 50.55a(g))
were changed on February 27, 1976, to require that facility inservice inspection (ISI) programs be periodically updated to later editions of the ASME, Boiler and Pressure Vessel Code,Section XI.
In order to eliminate conflicts between ISI requirements in the TS and those specified by regulation, 10 CFR 50.55a(g)(5)(ii) requires that TS be changed to reference 10 CFR 50.55a rather than contain details of a specific ISI program.
The surveillance requirement for ISI has already been revised to include this reference by BFN amendment numbers 98, 92, and 65.
Revising the LCO as described here will provide additional clarification and broaden the requirements of LCO 3.6.G to be similar to Standard Technical Specifications (STS).
The proposed change should not compromise nuclear safety since it results in an increase in TS requirements and is consistent with STS.
0122B
1
~
t h.J \\
t'
lp 4
~
ENCLOSURE 3 Determination of No Significant Hazards Consideration Descri tion of Amendment Re uest The proposed amendment would revise the technical specifications (TS) of Browns Ferry Nuclear Plant units 1, 2, and 3 to include not only the primary system but also the balance of ASME Code Class 1, 2, and 3 equivalent systems in the requirement to maintain structural integrity, Basis for Pro osed No Si nificant Hazards Consideration Determination The Commission has provided guidance for the application of criteria for no significant hazards consideration determination by providing examples of amendments that are considered not likely to involve significant hazards considerations.
Two of these examples are: "(ii) a change that constitutes an additional limitation, restriction, or control not presently included in the technical specifications.
(vii) A change to make a license conform to changes in the regulations where the license change results in very minor changes to facility operations clearly in keeping with the regulations."
The proposed amendments concerning the inclusion of ASME Code Class 1, 2, and 3 equivalent systems is in response to an NRC request regarding a change in 10 CFR 50.55a (g) which required a TS change.
Also the change will result in additional requirements which are similar to Standard Technical Specifications and are therefore encompassed by the above examples.
The Commission has also provided standards for determining whether a
significant hazards consideration exists as stated in 10 CFR 50.92.(c).
A proposed amendment to an operating license for a facility involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not:
(1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety.
The proposed changes will not significantly increase the probability or consequences of an accident previously evaluated or create the possibility of a new or different kind of accident from any accident previously evaluated because no operability or surveillance requirements for systems, structures or components used to terminate or mitigate accidents would be reduced and no equipment changes are involved, I
The proposed changes will not involve a significant reduction in a margin of safety since the changes conform to NRC guidance in STS and actually increase the requirements for structural integrity over the current TS requirement.
Since the application for amendment involves proposed changes that are encompassed by the criteria for which no significant hazards consideration exists and are encompassed by the above examples, TVA proposes to determine that the proposed amendments do not involve a significant hazards conside~gjIwn.