ML18025B360
| ML18025B360 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 02/20/1981 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18025B359 | List: |
| References | |
| NUDOCS 8103030674 | |
| Download: ML18025B360 (7) | |
Text
ENCLOSURE 1
PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS BROWNS FERRY NUCLEAR PLANT (5o-a6o)
0 LIMITING CONDITIONS. FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5.H Maintenance of Filled Dischar e Pi e The suction of the RCIC and HPCI pumps shall be aligned to the condensate storage
- tank, and the pressure suppres-sion chamber head tank shall normally be aligned to serve the discharge piping of the RHR and CS pumps.
The condensate head tank may be used to serve the RHR and CS discharge piping if the PSC head tank is unavailable.
The pressure indicators on the discharge of the RHR and CS pumps shall indicate not less than 3,isted below.
P1-75-20, 48 psig Pl-75-48 48 psig
'Pl-74-51 48 psig Pl-74-65 48 psig I.
Avera e Planar Linear Heat Generation Rate During steady state power operation, the Maximum Average Planar Heat Generation Rate (MAPHGR) for each type of fuel as
, a function of average planar exposure
, shall not exceed the limiting value shown in Tables 3.5.I-l, -2, -3, -4,.
and -5.
If at any time during operation it is determined by normal surveillance that the limiting value for
'PLliGR is being exceeded, action shall be initiated within 15 minutes to res'tore
'peration to within the prescribed limits. If the APLHGR is not returned to within the prescribed limi'ts within two (2) hours, the reactor shall be brought to the Cold Shutdown condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
Surveillance and corresponding action shall continue until reactor operation is within the prescribed limits.
J.
Linear lleat Generation Rate (LHGR)
During steady state power operation, the linear heat generation rate (LHGR) of any rod in any fuel assembly at any axial location shall not exceed the
~
following limits:
4.5.H Maintenance of Filled Dischar e Pipe Every month prior to the testing of the RHRS (LPCI and Containmen.
Spray) and core spray system, the discharge piping of these systems
'hall be vented from the high point and water flow determined.
2.
Following any period where t'e LPCI or core spray systems have not been required to be operable, the dis-charge piping of the inoperable sys-tem shall be vented from the high point prior to the return of the system to service.
3 ~
Whenever the HPCI or RCIC syste-is lined up to take suction from the condensate storage tank; the dis-charge piping of the HPCI and RCIC shall be vented from the high point of the system and water flow observe on a monthly basis.
4.
When the RHRS and the CSS are re-quired to be operable, the pressure indicators which monitor the dis-'harge lines shall be monitored daily and the pressure recorded.
I.
Maximum Avera e Planar L'near Heat Generation Rate (MAPLIIGR)
The IIAPLHGR for each type of fuel as a
function of average planar exposure shall be determined daily during reactor operation at ~ 25% rated thermal power.
J J.
Linear Heat Generation Rate (LHGR)
The LHGR as a function of core height for 7x7 fuel and as a constant for
- Sx8, 8xSR, and P8x8R fuel shall be
.checked daily during reactor operation at+25% rated t:hermal power.
)I I
for 8vS; 8x8R, and P8x8R fuel 13.4 Kw/ft; for 7x7 fuel, the maximum allowable, LHGR as ca1culated by the following equation:
159 4
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIRFHENTS ff LNGl<( LUCID,.(1 - (hl'/P)
(L/I,T)]
~ l)csign LllGR ~ 18.$ kW/fc d
(hl'/P)
= Haximum power spiking penalty max p p 2l' LT ~ Total core length
~ 12.0 ft
- l. ~ Axial position abov bottom of core If ac any tine during operation it is deter" mined by normal surveillance that the lim'ting valuo for LHCR is being exceeded, action shall bc initiaccd within 15 minutes to restore operation to ~ithin the prescribed limits.
If the LHCR is noc returned to within the prescribed'imits within two (2) hours, the reactor 'shall be brought to the Cold Shutdown condl.tion within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
Surveillance and corresponding action shall continue until reactor operation is within che prescribed 1imits.
'I K.
Minimum (:ricical Power Ratio (MCPR)
K.
Minimum Critical Power Ratio (MCPR)
Thc MCPR operating limit for BFNP, 2 cycle 4 is
,1.32 l..or 7K7, 1,27 for 8X8, 8x8R, and P8x8R fuel The.,e limits apply to steady state po-.
wer operation at rated power and flow.
For core flows other than rated, 'the YCPR shall be greater than the above limits times Kf.
Kf is chc value shown in. Figure 3.5.2.
HCPR shall be determined. daily during reactor po~er operation at 25K rated thermal po~er and following any change in power. level.
or dis tribucion tha t would cause operation with a limiting control rod pattern as described in the bases for Specification-3.3.
If ac any time during oper-ation ic is determined by normal surveill-ance chat the limiting value for MCPR is being exceeded, action'shall be initiated wi<<hin 15 minutes to restor'e operation to within the prescribed limits.
Xf the steady MCPR is noc returned to within the pre-scribed limits within two (2) hours, the reactor shall be brought to the Cold Shutdown condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />,
, 'surveillance and corresponding action shall continue until reactor operation is within the prescr"bcd limits.
L.
Rcoorcine Requirements I.'ny of the limiting values identified in Specifications 3.5.I, J, or K are exceeded and the specified action is
- taken, the event shall be logged and reported in' 30-day written report.
160
~<
3 ~ 5.J.Linear Heat General.
Rate (LHGR)
This specification assures that the linear heat generation rate.in any rod is less than the design linear heat generation if fuel pellet densification is postulated.
The power spike penalty specified
- is based on the analysis presented in Section 3.2.1 of Reference 1
as a:odified in References 2 and 3, and assumes a linearly increasing variation in axial gaps between core bottom and top, and assures with a 95% confidence, that no more than one fuel rod exceeds design linear heat generation rate due to pomer spiking.
-The LIIGR
( as a function of core heipht for 7x7 fuel and as a constant for 8x8.
- 8x8R, and P8x8R fuel' sh 11 bc el<>>eked daily dur-f<<c reactor operation at
> 252 porer to deter<<<Inc ff fuel burnup
~ or co<<-
trol rod <<<ovc<<<ent hss cau cd changes fn povcr dfstrfbutfo<<., }'r LllCR to bc a
1 faf tlag value bclov 25/ rated thcr<asl povcr, the R factor would have to be less than 0 24) ut<fch fs precluded by a considerable rsrgfn vhcn employing any pcr<<<fssfblc control rod pattern.
Hfa~~s< Critical Porer Rscfo HCPR At cor ~ thermal paver l>>vela less thsa or equal to 25, the reactor vfll be operation at c<fnf"ua recfrculstfoa pursp speed and the nod>>rator v fd b
v
>>ra or vo content vill
~ ve~
<<<asfl.
Pot all desfg<<at>>d control rod patterns v'<'
b
~ d a
p oye ar. th'fe point, oparatfag plant experience and there<sl hydraulic anal-ysis~
indicated that th>> resultfag HCPR value fs fa excess of r'equfres<eats by
~ corsfdersblc nsrgia.
'fifth this lov void content, any inadvertent core flov facr ~ sse vould only place operation fa a a<ore conservative sod>> rais-
~
tive to HCFR.
Th>> dsfly requfreaeat for calculatiag HCPP. above 25X rated therael pov>>r '1 o. suf!fcf>>at eface povar dfstrfbutfoa shifts are very slav vhea cher>>
hev>> aot b>>ea sfgafffcoat paver or coatrol tod ching Th
'es.
e requirement for HCFR vf1 calculating HCPR vh>>a s listfag control rod patte i
h d
ra s approac e
ea<<urea that v
1 be ksova fol)ovfag
~ change fn paver't paver shsp>>
(regardless of
~ftude) that could placs operation st
'a chore<al lfuft.
r.5.L.
~R>> ort'~
Pe ufrca>>ats The'CO's associated vfth aonitoriag the fuel rod operatf<<R coaditiaas are r>>q<<fr>>d to be e>>t at sll t!<aes, f.e., there fs as sllovabl>>
tf<ae ia vhfch the p'at caa kaovfagly exceed the Iinftfng values for HAPU!CR, LBCR, and HCFR.
It fo s requfreoeat, ae stated fn Speciffcatfons 3,5.I,.J, that if ct aay t'">> durfag st>>sdy state paver operatfca, ft is determined that (h>> lfaftfag values for H<<ZLHCR, LRCR, or HCPR arc exec>>C<d sctfoa is then fnftfsted to restore operation to vithfn the prescribed ff<efts.
Tnfs
~ ctfoo fs faftfat>>d as sooa as nore<sf surveillance indicates th=t aa op>>roti<<g ft >~s bc>>a r>>ached.
Each event involving steady st te op rsti b
ad e
oper <t oa
>>yond a speci! led shall be logged aad r>>ported quarterly.
It s<ust be reccgai ed th t ther>>
fs alvsyo an action vhich vould return aav of the para->>taro (HAPMCR, UlCR, o.
MCpR) to vfthfa prescribed if<sits, aooejy paver r<ructfon.
@der
>><oct cfrcu~staac>>s<
this vfll aot be the oaly alternative, H.
Rrter.ares
"~s] D>>aef!fcstfoa Rifects oa C>>serai Electric Boff;ag Pacer R sczoz Pue],," Suppl>>cents 6, 7, aad 8, MD.-10735, August 19?3
~
I 1 to Techafcsl Report oa Deasi! icatfoas oi Ceaeral El<<ctrfc p>>ector
- Fuels, De>>caber 14, 1974
('USA R>>gulacory S sff) f 4<.
Co<emaf catfoa.'.
A. Hoore to Z. S.
Hftche'.1, 'oa fffed C<,
for Fuel D>>asf! fcstfoa," Docx>>t 50-321, Harch 27, 1974,'
Gene eneric Reload Fuel Application, Licensi.ng Topical Report,.NEDE-24011-P-A, and Addenda.
169
ENCLOSURE 2 JUSTIFICATION Reference 1 documents the NRC staff position that ".
..it (is) acceptable to remove the 8x8 and 8x8R spiking penalty factor from the plant Technical Specification for those operating BMRs for
'hich it can be shown that the predicted worst-case maximum transient
- LHGRs, when augmented by the power spike penalty, do not violate the exposure-dependent safety limit LHGRs".,
The attached revision to the Browns Ferry ? reload 3 submittal I
c ntains the required information to remove the power spiking nalty from the technical, specifications.
Section 10 ("Rod thdrawal Error") and Appendix A ("Fuel Loading Error" ) include the nsification effect in the calculated LHGR.
REFERENCES 1.
"Safety, Evaluation of the General Electric Methods for the Consideration of Power Spiking Due to Densification Effects
~ in BWR 8x8 Fuel Design and Performance,"
Reactor Safety
- Branch, DOR, May 1978.
I