ML20197A588
| ML20197A588 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 02/19/1998 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20197A593 | List: |
| References | |
| NUDOCS 9803090298 | |
| Download: ML20197A588 (4) | |
Text
. _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ _
REACTIVITY CONTROL SYSTEMS 3/4.1.3 MOVABLE CONTROL ASSEMBLIES GROUP HEIGHT LIMITING CONDITION FOR OPERATION 3.1.3.1 All full length (shutdown and control) rods, shall be OPERABLE and positioned within i 18 steps (indicated position) when reactor power is s 85 %,
RATED THERMAL POWER, or i 12 steps (indicated position) when reactor power is
> 85% RATED THERMAL POWER, of their group step counter demand position within one hour after rod motion.
APPLICABILITY: MODES 1* and 2*
ACTION:
With one or more full length rods inoperable due to being immovable as a a.
result of excessive friction or mechanical interference or known to be untrippable, determine that the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, b.
With more than one full length rod inoperable or mis-aligned from the group step ccunter demand position by more than i 18 steps (indicated position) at 5 85 % RATED THERMAL POWER or i 12 steps (indicated position) at > 85% RATED THERMAL POWER, be in HOT STANDBY within 6
- hours, c.
With one full length rod inoperable due to causes other than addressed by ACTION a, above, or mis-aligned from its group step counter demand position by more than i 18 steps (indicated position) at 5 85 % RATED THERMAL POWER or i 12 steps (indicated position) at > 85% RATED THERMAL POWER, POWER OPERATION may continue provided that within one hour either:
1.
The rod is restored to OPERABLE status within the above alignment requirements, or 2.
The remainder of the rods in the bank with the inoperable rod are aligned to within i 18 steps (indicated position) at 5 85 % RATED THERMAL POWER or i 12 steps (indicated position) at > 85% RATED THERMAL POWER of the inoperable rod while maintaining the rod sequence and insertion limits in the COLR per specification 3.1.3.5. The THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.5 during subsequent operation, or 3.
The rod is declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied. POWER OPERATION may then continue provided that:
9803090298 900219 PDR ADOCK 05000272 P
.,...+=uias am u z.wepcions 4.10.2 and 3.10.3.
SALEM - UNIT 1 3/4 1-18 Amendment No. 202 Rev i sed by l e tte r d td February 19_ loo 8
O e
TnB PAGE DrrElfftCIIALLY LE7f ALANE l
l e
POWER DISTRIBUTION LIMITS EASES.
3/4.2.2 and 3/4.2.3 HEAT FLUX AND NUCLEAR ENTHALPY HOT CHANNEL AND RADIAL PEAKING FACTORS - To(Z), Fm and F,y(Z)
The limits on heat flux and nuclear enthalpy hot channel factors ensure that 1) the design limits on peak local power density and minimum DNBR are not exceeded and 2) in the event of a LOCA the peak fuel clad temperature will not exceed the 2200*F ECCS acceptance criteria limit.
Each of these hot channel factors are measurable but will normally only be determined periodically as specified in Specifications 4.2.2 and 4.2.3.
This periodic surveillance is sufficient to insure that the hot channel factor limits are maintained provided:
Control rod in a single group move together with no individual a.
rod insertion differing from the group demand position by more than the allowed rod mislagnment, b.
Control rod groups are sequenced with overlapping groups as described in Specification 3.1.3.5.
l c.
The control rod insertion limits of Specifications 3.1.3.4 and 3.1.3.5 are maintained, d.
The axial power distribution, expressed in terms of AXIAL FLUX DIFFERENCE, is maintained within the limits.
The relaxation in F"a as a function of THERMAL POWER allows changes in the radial power shape for all permissible rod insertion lindts.
fm will be maintained within its limits provided conditions a thru d above, are maintained.
When an To measurement is taken, both experimental error and manufacturing tolerance must be allowed for 5% is the appropriate allowance fo: a full core map taken with the incore detector flux mapping system and 3%
is the appropriate allowance for manufacturing tolerance.
When F"a is measured, experimental error must be allowed for and 4% is the approp*iate allowance for a full core map taken with the incore detection system. The specified limit for F"a also contains an 8% allowance for uncertainties which mean that normal operation will result in F m t.F* m /1.08 where F" a is the limit of RATED THERMAL POWER (RTP) specified in the CORE OPERATING LIMITS REPORT (COLR).
The 8% allowance is based on the following considerations:
SALEM - UNf? 1 B 3/4 2-4 Amendment No.202 R e v i s e d by l e t t e r d t d Fehnmrv 10, 1oog
- 'T R.vA 7*: N : l'.,Y
- 8ercent of agt,q 7% erm sl Bewer 10 0 %
\\
so.
I i
40%
70 %
(=. Tars rtun otgrer.ne, 40%
50%
40 %
30%
20%
10 %
O 3
.tet 0
10 %
20%
L gge0ISATOS AX1AL PLUE OtFFERENCS pp g age 34 ffPtCAL IN90 CATES AXtAL FtuX 06FFERE80C8 vtASUS THERI8AL POW 88 notee se cota rigure a ter Astu t fimais
.se...
-=
,_. m,,