ML20011E412

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Proposed Tech Specs Re Acceptance Criteria for Absolute & Relative Position Indicator Channels
ML20011E412
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 02/01/1990
From:
TOLEDO EDISON CO.
To:
Shared Package
ML20011E409 List:
References
1750, NUDOCS 9002130369
Download: ML20011E412 (8)
v • d • e


Text

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Docket Mumber So.346' '? $ !

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nt 3 ' REACTIVITY CONTROL SYSTEMS a ttcc 3/_4.1. 3 MOVABLE CONTROL ASSEMBLIES GROUP HEIGHT - SAFETY AND REGULATING R00 GROUPS LIMITING CONDITION FOR OPERATIONS  !

3.1.3.1 All control (safety and regulating) rods shall be OPERABLE and i

positioned within ,+ 6.5% (indicated position) of their group average height.  :

APPLICABILITY: MODES 1* and 2*,

ACTION:

t

a. With one or more control rods inoperable due to being immovable as 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 one hour and be in at least HOT STANDlY 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 control rod inoperable or misaligned from its group average height by more than + 6.5% (indicated '

position), be in at least NOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,

c. With one control rod inoperable due to causes other than i addressed by ACTION a, above, or misaligned from its group average height by more than + 6.51 (indicated position), POWER OPERATION may continue proviied that within one hour either:
1. The control rod is restored to OPERABLE status within the above alignment requirements, or ,
2. The control rod is declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is. satisfied.

POWER OPERATION may then continue provided that:

a) An analysis of the potential ejected rod worth is [

L performed within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and the rod worth is deter-l mined to be < 1.05 Ak at zero power and < 0.65%

ak at RATED THERMAL POWER for the remainTer of the fuel cycle.

l b) The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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  • 5ee Special Test Exceptions 3.10.1 and 3.10.2.

DAVIS-BESSE, UNIT 1 3/4 1-19 9002130369 900201 b ADOCK 0500 6 ,

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REACTIVITY CONTROL' SYSTEM 5 l

ACTION: (Continued) i e) A power distributiga map is obtained from the intere  !

detectors and F0 F"gare verified to be within their limits  !

within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. ,

t Either the TEIRMAL p0VER level is reduced to < 605 of the t MMAL POVER allovable ior the restter ecolant pump l

.atnation within one hour and within the neat 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the i eign Flux Trip setpoint is reduced to < 705 of the TERRMAL '

Pov3:R allowable for, the reactor coolant pump combination, or l t

e) The remainder of the rods in the group with the inoperable rod are aligned to within 6.3% of the inoperable rod within ,

i one hour while maintaining the rod sequence, insertion and -i overlap limits of Figure 3.1-2 and 3.1-31 the TEIRNAL 70VER t level shall be restricted pursuant to Specification 3.1.3.6  :'

during subsequent operation.

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StFIRILLANCE REQUIREMENTS

~

i 4.1.3.1.1 The position of each control rod shall be determined to be within the  !

group average height limit by verifying the individual rod positions at least -

once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the Asymmeeete-7 f 7 '  !

e individual rod position (s) o th 7 1 tg Ct.;;;;ri is inoperable rod (s), vit operabl .. g;;;.try, t least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. ,

ks metse wtm.% aZ: ,,gyl-4.1 3.1.2 control r not u y inserted shall be determined to ' - - -

OPERABLE by movement of at least 22 in any one direction at least once every 31 days.

i I

DAVIS-8 ESSE, UNIT 1 3/4 1-20 Amendment No.135

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' Dock;t Cumb?r 50-346

. Lic:ns? Numb:r NPF-3  ;

l Serial Number 1750 Attachment 3 Page 3 J

REACTIVITYCONTROLSYSTEMj, l

J GROUP HEIGHT - AXIAL POWER SHAPING ROD GROUP LIMITING CONDITION FOR OPERATION  !

3.1.3.2 All axial power shaping rods (APSR) shall be OPERABLE, unless fully withdrawn, and shall be positioned within + 6.5% (indicated ~

position) of their group average height. '

APPLICABILITY: MODES 1* and 2*.

l ACTION: I With a maximum of one APSR inoperable or misaligned from its group average height by more than + 6.5% (indicated position), operation may i continue provided that withiii 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:

a. The APSR group is positioned such that the misaligned rod is' ,

restored to within limits for the group average height, or

b. It is determined that the imbalance limits of Specification 3.2.1 are satisfied and movement of the APSR group is pre- .

vented while th6 rod remains inoperable or misaligned.  :

SURVEILLANCE REQUIREMENTS r

4.1.3.2.1 The position of each APSR rod shall be determined to be i within the group average height limit by verifying the individual rod posi 1 er urs except during time intervals when the - . . . .. ... is inoperable, then vertfr _ ndi- ;

vidua ro pos ion s o e ro s), wit

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at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, g .g Mv*me% wapa..

4.1.3.2.2 Unless all APSR are fully withdrawn, the APSR shall be determined to be OPERABLE by moving the APSR rods at least 2% at least once every 31 days.

  • See Special Test Exceptions 3.10.1 and 3.10.2. '

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DAVIS-BESSE, UNIT'l 3/4 1-21 l

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REACTIVITY CONTROL SYSTEMS 1 I

POSITION INDICATOR CHANNELS

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LIMITING CONDITION FOR OPEPATION i

3.1.3.3 All safety, regulating and axial power shaping control rod f absolute position indicator channels and relative position indicator '

channels shall be OPERABLE and capable of determining the control rog 3mp .

positions within + , averay APPLICABILITY _: MODES 1 and 2. l ACTION:

a. With a maximum of one absolute position indicator channel per  ;

control rod group or one relative position indicator channel i per control rod group inoperable either:

1. Reduce THERMAL POWER to < 60% of the THERMAL POWER allow-able for the reactor cooTant pump combination and reduce-the High Flux Trip Setpoint to < 70% of the THERMAL POWER allowable for the reactor coolan,,t pump combination within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or
2. Operation may continue provided: ,

a) The position of the control rod with the inoperable position indicator is verified within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> by actuating its 0%, 25%, 50% 75% or, 100% position reference indicator, and 4

b) The control rod group (s) containing the inoperable position indicator channel is subsequently maintained '

at the 0%, 25%, 50%, 75% or,100% withdrawn position and verified at this position at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter, and c) Operation is within the limits of Specification 3.1.3.6. .

b. With more than one .___ m ,. position indicator channel inoperable, operation in MODES 1 and 2 may continue for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />' provided all of th - ' " ' ": position indicator channels are OPERABLE.

DAVIS-BESSE,. UNIT 1 3/4 1-22

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i Dock;t Number 50-346 t License Number NPF 3 -l Serial Number 1750

'l Attachment 3 Page 5 I

REACTIVITY CONTROL SYSTEMS ,

t POSITION INDICATOR CHANNELS (Continued)

SURVEILLANCE REQUIREMENTS i

4.1.3.3 Each absolute and relative position indicator channel shall be determined to be OPERABLE by verifying th6t the relative position indic channels and the absolute position indicator channels agree within 6ft' at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the -

at:-:;\,

R;d F:;1t Circuitry is inoperable, then compare the relative position indicator and absolute position indicator channel (s) of the rod (s) with operable c ' "' + ri--"itr/ at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, r me ,h,.

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DAVIS-BESSE, UNIT 1 3/4 1-23 l

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REACTIVITY CONTROL SYSTEMS $f '

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BASES '

l 3/4.1.2 BORATION SYSTEMS (Continued)  !

stable reactivity condition of the reactor and the additional l restrictions prohibiting CORE ALTERATIONS and positive reactivity change 1 in the event the single injection system becomes inoperable.

The boron capability required belov 200'F is sufficient to prnvide a  !

SHUTDOVN MARGIN of 1% Ak/k after xenon decay and cooldown from 200'F to 70'F. This condition requires either 600 gallons of 7875 ppm borated ^

vater from the boric acid storage system or 3,000 gallons of 1800 ppe borated water from the borated water storage tank.

The bottom 4 inches of the borated water storage tank are not available, and the instrumentation is calibrated to reflect the available volume.

All boric acid tank volume is available. The limits on vater volume, and boron concentration ensure a pH value of between 7.0 and 11.0 of the solution recirculated within containment after a design basis accident. ,

The pH band minimises the evolution of iodine and ainimizes the effect of chloride and caustic stress corrosion cracking on mechanical systems and components.

The OPERABILITY'of one boron injection system during REFUELING ensures that this system is available for reactivity control while in MODE 6.

3/4.1.3 MOVAELE CONTROL ASSEMBLIES

  • The specifications of this section (1) ensure that acceptable power distribution limits are maintained, (2) ensure that the minimum SHUTD0VN MARGIN is maintained, and (3) limit the potential effects of a rod ejection accident. OPERABILITY of the control rod position indicators is required to determine control rod pcsitions and thereby ensure compliance with the control rod alignment and insertion limits.

The ACTION statements which permit limited variations from the basic ,

requirements are accompanied by additional restrictions which ensure that the original criteria are met. For example, misalignment of a safety or regulating rod requires a restriction in THERMAL POVER. The reactivity vorth of a misaligned rod is limited for the remainder of the fuel cycle to prevent exceeding the assumptions used in the safety analysis.

The position of a rod declared inoperable due to misalignment should not be included in computing the average group position for determining the OPERABILITY of rods with lesser misalignments.

DAVIS-BESSE, UNIT 1 B 3/4 1-3 Amendment No.123

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i Dock;t Numb 3r 50 346

  • i Licens3 Numb 3r NPF-3  !
  • Soiial Numb 3r 1750 '

Attachment 3 Page 7 l REACT!'.*!"T CONTROL SYSTD!S BASES r .

l 3/4.1.3. MOVABLE CONTROL ASSEMBLIES (Continued)

The maximum rod drop time permitted is consistent with the assumed rod drop time used in the saiety analyses. Massurement with Tavs a 325'T and with re-  ;

actor coolant pumps operating ensures that- the measured drop times will be representative of insertion times experienced during a reactor trip at operat- i ing conditions.

Control rod positions and OPERABILITY of the rod position indicators are re- -

quired to be verified on a nominal basis of once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with frequent verifications required if an automatic monitoring channel is inoperable. These ,

verification fr are adequate for assuring that the applicable LCO's ,

are satisfied. n sat,A--_ ,

Technical Specification 3.1.3.8 provides the ability to prevent excessive ,

power peaking by transient xenon at RATED THERMAL POWER. Operating restrie- L tions resulting frem transient xenon power peaking, including xenon-f ree startup, are inherently included in the limits of Sections 3.1.3.6 (Regulat-ing Rod Insertion Limits) 3.1.3.9 (Axial Power Shaping Rod Insertion Limits),

and 3.2.1 (Axial Power Imbalance) for transient peaking behavior bounded by the following factors. For the period of cycle operation where regulating rod groups 6 and 7 are allowed to be inserted at RATED THERMAL POWER, an 8%

peaking increase is applied at or above 92177. An 18% increase is applied below 92: FF. For operation where only regulating rod group 7 is allowed to ,

be inserted at RATED THERMAL POWER, a 5% peaking increase is applied at or above 92% T7 and a 13 increase is applied below 92: TP.

If these values, checksd every cycle, conservatively bound the peaking sf fects -

of all transient xen6n, than the need for any hold at a power level cutof f be-low RATED THERMAL POWER is precluded. If not, either the power level at which the requirements of Section 3.1.3.8 must be satisfied or the above-listed f ac-tors vill be suitably adjusted to preserve the LOCA linear heat rate limits.

The li=1tation on axial ' power ' shaping red insertion is necessary to ensure that power peaking limits are not exceeded.

6 DAVIS-BESSE. UNIT 1 B 3/4 1-4 Amendment No. M ,45 1

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"; Lic :co Number NPF 3  ;

Serial Number 1750 j Attachment 3 J Page 8 '

INSERT A A 1.5% group average position uncertainty is applied to the rod index curves, i Therefore, the position indicators must be capable of supporting this accuracy. The Surveillance Requirement ensures this accuracy by keeping the RPI calibrated to a "knovn" position as indicated by the API. Using the API as a "known" position is valid provided two consecutive reed switched are not inoperable. Having one entire string, (1. e., every other reed switch) inoperable is acceptable.

A specific surveillance of the reed switches is not required because:

1) When one or more reed switch fails closed a large API indication of asymmetry occurs.
2) Two failed open reed switches in series result in a large indication of asymmetry.
3) Failed open reed switches not in series (up to every other switch) are bounded by the analysis.

Therefore, a reed switch condition not bounded by the analysis vill be indicated by API system asymmetry indications.

I t

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