ML20073K911
| ML20073K911 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 05/06/1991 |
| From: | DUQUESNE LIGHT CO. |
| To: | |
| Shared Package | |
| ML20073K903 | List: |
| References | |
| NUDOCS 9105130136 | |
| Download: ML20073K911 (11) | |
Text
_ _ _ _ _ _ _- -
ATTAClitil:14T A-1 Beaver Valley Power Station, Unit 11 0. 1 Proposed Technical Specification Change No. 1A-190 Rerise the Technical Specifications as follown:
Remove _Eage InserLPime 3/4 4-23 3/4 4-23 i
l i
5 9105130136 91050A FDR ADOC K 0500ni::.;
P PDR
M R COOLANT..SYSTEb(
SURVIILIANCE REQUIRE 303fTS 4.4.9.1 a.
The Reactor Coolant System temperature and pressure shall be determined to be within the limits at least once per 30 minutes during system heatup, cooldown, and inservice leak and hydrostatic testing operations.
b.
The Reactor Coolant System temperature and pressure conditions shall be determined to be to the right of the criticality limit line within 15 minutes prior to achieving reactor criticality.
E t-re'1L c +o r Ve S Ce l t% 4 e t I rr* A ' " Yb ^
C-su e ve ; I ( q,, ce epec. m e., c w II l>e c cew ad owl ega >>n nex m acco<dovcc gi.'y k to ( F12 cro, t
m malcrea I (I mye5
,4 e,s/i y l-l,
/v clJ 4 er m iet e Iiw roso I hs of Sece esamum 4,ons d(co(e,-41e z.
md al{ be used io up clatt Pt]v r e s 3 '/
2 3 4/ - 3 BEAVER VALLEY - UNIT 1 3/4 4-23 fit oposen WoeT&M)
A T T A Cll M I:!J T A - 2 Beaver Valley Power Station, Unit 11 0. 2 Proposed Technical Speci fication Change 110, 2A-54 Revice the Technical Specifications an follown:
Eppove j' age Innert Page 3/4 4-30 3/4 4-30 i
i 4
i E
l l
t i
i i
(
l
)
1
l l
REACTOR COOLANT SYSTEM 3/4.4.9 PRESSURE / TEMPERATURE LIMITS REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION 3.4.9.1 The Reactor Coolant System'(except the pressurizer) temperature and pressure shall be limited in accordance with the limit lines shown on Figures 3.4-2 and 3.4-3 during heatup, cooldown, criticality, and inservice leak and hydrostatic testing with:
a.
A maximum heatup cf 60'F in any 1-hour period, b.
A maximum cooldown of 100'F in any 1* hour period, and c.
A maximum temperature change of ( 5'F in any 1-hour period during hydrostatic testing operations a6ove system design pressure.
APPLICABILITY:
H0 DES 1, 2, 3, 4, and 5.
ACTION:
With any of the above limits exceeded, restore the temperature and/or pressure to within the limit within 30 minutes; perform an analysis to determine the' effects of the out-of-limit condition on the fracture toughness properties of the Reactor Coolant System; determine that the Reactor Coolant System remains acceptable for continued operations or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce the RCS T,yg and pressure to less than 200'F and 500 psig, respectively, within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REOUIREMENTS 4.4.9.1 a.
The Reactor Coolant System temperature and pressure shall be determined to be within the limits at least once per 30 minutes during system heatup, dooldown, and inservice leak and hydrostatic testing operations, b.
I k Reactor Coolant System temperature and pressure conditions shall htermined to be to the right of the criticality limit line within g nutes prior to achieving reactor criticality.
C. 3, e. rea cler. ve5ce J MAfen a.( (rradiM dn Su rveil/ance S bec Im eM Sk.t (l bc Ve m e scl w-l ey.Qtwot ec/ th a ccordance,v N H t o c Fit 50, Appo, Ax //,
fv la e le<<m n e en ww A *'r' d fro TJa resvits of C btmg esc t c%n i n d t h r s k,fer h es.
Rese J(
60 ned k v(> ck N Dij v rc 5, 3 M - ?. evv/ 3M-3 BEAVER VALLEY - UNIT 2 3/4 4-30
/?OfOS6D N-l;L Ol/% l
ATTACHMl:11T B Beaver Valley Power Station, Unit !! o. 1 and 2 Proposed Technical Specification Change 11 0. lA-190/2A-54 REVIS10!J OF 'I ECll!!ICAL DPECI PICATIO!J 3.4.9.1 m...-
A.
DESCRI PTI O!J OF AME!JDMEtJT REQUEST The proposed amendment would add a surveillance requirement to Technical Specification 3/4.4.9, PRESSUPE/ TEMPERATURE LIMJTS REACTOR COOLA!JT SYSTEM.
The new curveillance requirement would be item 4.4.9.1.c.
Jurveillance Requirement 4.4.9.1.c Will provide for the removal and examination of the reactor vessel material irradiation curveillance specimens in accordance with 10CFR50, Appendix 11.
'1 h e nurveillance requirement would also state that the results of these exaninationr chall be used to update F i gu re r.
3.4-2 and 3.4-3.
B.
BACECROUllD On January 4,
1991, the !JRC issued Generic Letter 91-01, lle nov a l of the Schedula _jor the Withd rjlwal of Reactg __ Vessel Ma t e r i a_1 SPe cE e_On fron Technical Spec _i tlicalions.
Thin Generic Letter provide
- for the removal of the schedule since it duplicaten the controls on changen to this schedule that have been establiched by 10C1 R50, Appendix H.
Prior to the icouance of Generic Letter 91-1, Beaver Valley had submitted and obtained a
change to the Units 1 and 2 Technical Specification to delete both Table 4.5-5,
" Reactor Vessel Material Irradiation Surveillance Schedule" and the annociated Surveil 1ance Requirement 4.4.9.1.c.
This amendment requent neekt to instate a
reference to 10CFRSO, Appendix H and reinstate the requirement that the results of the material examinationo shall be used to update Iigures 3.4-2 and 3.4-3 (RCS heatup and cooldown curves).
This would, in oftect, restore a part of the previously deleted Surveillance 4.4.9.1.c.
C.
JUSTIrlCATION The proposed amendment request would bring Specification 3.4.9.1 into agreennnt with the outline of Generic Letter 91-01.
It would also further ensure that Figures 3.4-2 and 3.4-3 were updated tollowing reactor vessel sample exaLination.
Currently the requirement for updating the heatup and cooldown curves is iound only in the UFSAR.
D.
SAFETY A!!ALYSIS The proposed change is considered to be administrative in nature and will not reduce the safety of the plant.
Adding the additional surveillance requirement will further ensure that Figures 3.4-2 and 3.4-3 are updated following vessel irradiated sample examination.
- Also, this change will not affect the reactor vessel surveillance program or alter any plant contiguration or mode of operation.
Proposed Technical Specification Change No. lA-190/2A-54 Page 2 1:.
NO SIGNIFICANT llAZARDS FVALUATION The no significant hazard considerations involved with the proposed amerdment have been evaluated, focusing on the three standards set forth in 10 CFR 50.92(c) as quoted below:
The Comm.ssion may make a final determination, pursuant to the procedures in paragraph 50.91, that a proposed amendment to an operating license for a
facility licensed under paragraph 50.21(b) or paragraph 50.22 or for a testing facility involves no significant hazards consideration, 11 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 trom any accident previously evaluated; or (3)
Involve a significant reduction in a margin of safety.
The following evaluation is provided for the no significant hazards consideration standards.
1.
Does the change involve a
significant increase in the probability or consequences of an accident previously evaluated?
No.
The proposed change will not affect the reactor vessel material surveillance program.
Implementation of the proposed change will add a
surveillance requirement that will further ensure that the reactor vessel material irradiation surveillance specimens be removed and examined in accordance with
- 10CFR50, Appendix 11.
The surveillance will also further ensure that the results of the specimen examination are used to update the RCS heatup and cooldown curves of Figures 3.4-2 and 3.4-3 respectively.
Therefore, these changes are considered to be administrative and do not significantly increase the probability or consequences of an accident previously evaluated.
2.
Does the change create the possibility of a new or different kind of accident from any accident previously evaluated?
No.
These changes will not alter any plant configuration or mode of operation.
Compliance with existing regulations will ensure continued confidence in the reactor vessel material properties.
Therefore, the proposed change will not create the possibility of a new or different kind of accident from any previously evaluated.
f, Proposed Technical Specification Change IJo. 1A-190/2A-54 Page 3
~,.
Does the change involve a significant reduction in a margin of aafety?
!Jo.
Evaluation of the reactor vessel material for radiation embtjt".lement will not be altered by this change.
Adding Surveillance Requirement 4.4.9.1.c would further ensure that Figures 3.4-2 and 3.4-3 were updated following reactor vessel sample examination.
Therefore, the proposed amendment will not involve a significant reduction in the margin of safety.
F.
110 SIGtJIFICA!JT HAZARDS CO!JSIDERATIO!J DETERMI!JATIO!J Based on the considerations expressed above, it is concluded that the activities associated with this license amendment request satisfies the no significant hazards consideration standards 01 10 CFR 50.92(c)
- and, accordingly, a
no significant hazards consideration finding is justified.
G.
E!JVIRONME!JTAL EVALUATIO!J The proposed changes have been evaluated and it has been determined that the changes do not involve (i) a significant hazards consideration, (ii) a si~ni'.'icant change in the types or significant increase in the amot its of any effluents that may be released
- offsite, or (iii) a s anificant increase in individual or cumulative occupational rad inn exposure.
Accordingly, the proposed changes meet the el:-
'ty criterion for categorical exclusion set forth in 10 CFR
'(c) (9).
Therefore, pursuant to 10 CFR 51.22 (b), an enviror,.
al assessment of the proposed changes is not required.
ATTAcitMI.!JT C-1 15eaver Valley Power Station, Unit fi o. 1 Propored Technical Specification Change llo. 1A-100 Typed page:
3/4 4-23 I
I l
)
L I
i 4
1 I
r i
I
i l
IdliO10}L. COO 14ff[L 0Y.STl;fi SultVEII 1 A!!CE Iti:QUlltEMI:!JTS
= = = = =. =
=
=. = =.==:
.:==,====_=======,====.=_a
.== = =
4.1.9.1 a.
The iteactor Coolant System temperature and pressure chall be determined to be within the limits at least once per 30 minuten during nyctem heatup, cooldown, and inservice leak and hydrostatic testing operations.
b.
The 11ea c t o r Coolant System temperature and prennure conditionc nhall be determined to be to the right of the criticality limit line within 15 minuten prior to achieving reactor critic 1]ity, c.
The reactor vousel material irradiation surveillance specimens shall be removed and examined in accordance with 10 CI'R 5 0, Appendix 11, to determine changen in material properties.
The results of these examinationn shall be used to update l'ig u re s 3.4-2 and 3.4-3.
13EAVER VALLEY - UllIT 1 3/4 4-23 (Proposed Wording)
A T I A C }l M I.!1 T C - 2 Beaver Valley l'ower Station, Unit 11 0. ?
I'roponed Technical Specifleation Change 110. 54 Typed page:
3/4 4-30 i
b
!i i
i i
l<!' ACI OR COOLAf1T_ SYp'll M i
i i
M4._4. 9. l'R ES FU k lZTL M l 1;8 ATU R IL l4 M I TO B OMl1 OR..CO01./WT_ DYSTFM LIMITING CO!1DITION l'OR OPERATIO!J
=
= = =. - -
3.4.9.1 The Reactor Coolant System (except the prennurizer) torperature and preocure chall be limited in accordance with the 1imit 1inen shown on l'iguren 3.4-2 and 3.4-3 during heatup, cooldown, criticality, and inservice l eal; and hydrontatic tenting with a.
A maximum heatup of 60*T in any 1-hour period, b.
A naxinum couldown of 100*r in any 1-hour period, and c.
Is na >:i mu n temperature change of 5 5'r in any 1-hour period during hydrontatic testing operationn above nyntem denign p renu re.
bINI CIEL I:llY
- MODI'S 1,
2, 3,
4, and S.
tWTLou:
With any of the above 1inits exceeded, rentore the temperature and/or prenuure to within the 1imit within 30 minuten; portorm an analynin to deternine the offects of the out-of-limit condition on the
!racture toughnenn propertien of the Reactor Coolant Syntem; determine that the Reactor Coolant System remains acceptable for continued operations or be in at least ilOT STA!1DhY within the next 6 hourn and reduce the RCS T
and prensure to lenn than 200"F and 5nD pnig, renpectively, within N following 30 hourn.
SURVEl LL/JJCE RI: OUI RI:MENTS
=
=
=- -
= = = = =.
= _
=
4.4.9.I a.
The Reactor Coolant Syntom temperature and prensure chalI be determined to be with.in the limitn at least once per 3u minutes during nyntem heatur., cooldown, and innervice l ea };
and hydroutatic tenting operations.
b.
The Reactor Coolant Systen<
temnerature and pressure conditionn shall be determinect to be to the right of the criticality limit line within.5 minuten prior to achieving reactor criticality, c.
The reactor vesnel material irradiation surveillance specimens chall be removed and examined in accordance with
to determine changen in material properties.
The results of these examinations chall be used to update Figures 3.4-2 and 3.4-3.
BEAVI:R VALLEY - Ul11T 2 3/4 4-30 (Proposed Wording)
_ _ _ -.