Text

Amend 51 to License DPR-66,revising Tech Specs on Rod Misalignment,Core Peaking Factor Limits & Associated Parameters
	ML20054J438
Person / Time
Site:	Beaver Valley
Issue date:	06/14/1982
From:	Varga S; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20054J439	List: ML20054J438; ML20054J441; ML20054J443;
References
	NUDOCS 8206280681
	Download: ML20054J438 (24)
	v • d • e

.

f rutoq)i s

UNITED STATES p

EE NUCLEAR REGULATORY COMMISSION y,, Y :,"

E WASHINGTON, D. C. 20555

Q DUQUESNE LIGHT COMPANY OHIO EDIS0N COMPANY PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVER VALLEY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY'0PERATING LICENSE Amendment No. 51 License No. DPR-66 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Duquesne Light Company, Ohio Edison Company, and Pennsylvania Power. Company (the licensees) dated February 23, 1982, as amended by letters dated April 21, April 26, May 5, May 26, June 1 and June 10, 1982, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commistion; C.

There is reaEna~ble assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisf.ied.

B206280681 820614 4

PDR ADDCK 05000334 i

P PDR

. 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-66 is hereby amended to read as follows:

(2)

Technical Specifications The-Technical Specifications containined in Appendices A and B, as revised through Amendment No. 51, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

F R THE NUCLEAR F ULATORY COMMISSION (F'

b. ---

k e

arga, Operating Reactors ra ch No.1 Division of Licensin

Attachment:

Changes to the Technical Specifications Date of Issuance:

JUN 141982

~

e i

4 ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 51 TO FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 Revise Appendix A as follows:

Ren'ove Paces-Insert Paces 2-6 2-6 3/4 1-18 3/4 1-18

~'

3/4 1-19 3/4 1-19 3/4 1-19A 3/4 1-20 3/4 1-20 3/4 1-20A 3/4 1-20A 3/4 1-20B 3/4 1-21 3/4 1-21 3/4 1-22 3/4 1-22

'3/4 1-23 3/4 1-23 3/4 1-23A 3/4 10-2 3/4 10-2 3/4 10-6 3/4 10-6 B3/4 1-3 B3/4 1-3 B3/4 1-4 B3/4 1-4 3/4 2-6A 3/4 2-6A.

3/4 2-8 3/4 2-8 3/4 2-9A B3/4 2-5 B3/4 2-5 6-16 6-16 6-17 6-17

l TABLE 2.2-1 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS 9g FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES n

i

1. Manual Reactor Trip Not Applicable Not Applicable l

l~

Low Set'oint - 1 25% of RATED Low Setpoint - 1 26% of RATED 3

Q

2. Power Range, Neutron Flux p

TilERMAL POWER TilERMAL POWER l

c-$

liigh Setpoint - 1 109% of RATED liigh Setpoint - 1 110% of RATED H

TilERMAL POWER TilERMAL POWER

3. Power Range, Neutron Flux, 1 5% of RATED TilERMAL POWER with 1

5% of RATED THERMAL POWER 5

liigh Positive Rate a time constant > 2 seconds with a time constant > 2 seconds

4. Power Range, Neutron Flux,

< 5% of RATED ElERMkl POWER with

< 5.5% of RATED TilERMAL POWER liigh Negative Rate a time constant > 2 seconds with a time constant > 2 seconds

'?

5. Intermediate Range, Neutron 1 25% of RATED TilERMAL POWER 1 30% of RATED THERMAL POWER l

Flux i

5 1 5 1

3 x 10 counts per second

6. Source Range, Neutron Flux 10 counts per second 1

i

7. Overtemperature AT See Note 1 See Note 3 l

l

8. Overpower AT See Note 2 See Note 3 l

9. Pressurizer Pressure--Low

> 1945 psig

> 1935 psig e

g

10. Pressurizer Pressure--High 1 2385 psig 1 2395 psig l

M j

E

11. Pressurizer Water Level--liigh 1 92% of instrument span 1 93% of instrument span j

M i

5

12. Loss of Flow

> 90% of design flow

> 89% of design flow per loop per loop i

2P i

Design flow is 88.500 gpm per loop.

j g

1 i

i

?

REACTIVITY C0tiTROL SYSTEMS 3/4.1.3 MOVABLE CONTROL ASS MBLIES GROUP HEIGHT LIMITING CONDITION FOR OPERATI0tl 3.1.3.1 All full length (shutdown and control) rods shall be OPERABLE and positioned within + 12 steps (indicated position, as determined in accordance with Specification 3.1.3.27correspondingtotheirrespectivegroupdemandcounterposition.

A_PPLICABILITY: MODES 1* and 2*

ACTION:

~

a.

With one or more full length 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 satisfidd within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With more than one full length rod inoperable or misaligned from the group demand counter position by more than + 12 steps (indicated position determined in accordance with Specification 3.1.3.2), be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

i c.

With one full length rod trippable but inoperable due to causes other than addressed by ACTION a, above, or misaligned from its group demand counter position'by more than + 12 steps (indicated position determined in accordance with Specification 3.1.3.2), 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 rod is declared inoperable and the remainder of the rods in the group with the inoperable rod are' aligned to within + 12 steps of the inoperable rod while maintaining the rod sequence and insertion limits of Figures (3.1-1) and (3.1-2); the THERMAL POWER level shall be restricted pursuant to Specification (3.1.3.6) 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:

a) The THERMAL POWER level is reduced to less than or equal to 75%

of RATED THERMAL POWER within the hour and, within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the high neutron flux trip setpoint is reduced to less than or equal j

to 85% of RATED THERMAL POWER.

BEAVER VALLEY - UNIT 1 3/4 1-18 AMENDMENT NO. 51 f

u

LIMIT!tiG C0flDITI0ft FOR OPERhTIO?i (Contjnued) b) The SHUTOOWN MARGIti requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

t c) A power distribution map is obtained from the mcvable incore detectors and F (Z) and F H are verified to be within their 0

limits within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

d) A reevaluation of each accident analysis of Table 3.1-1 is performed within 5 days; this reevaluation shall confirm that the previously analyzed results of these accidents remain valid for the duration of operation under these conditions.

SURVEILLAfiCE REQUIREMENTS 4.1.3.1.1 Each shutdown and control rod not fully inserted in the core shall be determined to be OPERABLE by movement of at least 10 steps in any one direction at least once per 31 days.

i i

i t

i 05ee Special Test Exceptions 3.10.2 and -3.10.4

' BEAVER VALLEY - UNIT 1 3/4 1-19 AMENDMENT NO. 51 l

-- n _

TABLE 3.1-1 ACCIDENT ANALYSES REQUIRING REEVALUATION IN THE EVENT OF Ah IfiOPERABLE FULL OR PARI LEt,GTH ROD Rod Cluster Control Assembly Insertion Characteristics Rod Cluster Ccntrol Assembly Misalignment Loss of Reactor Coolant From Small Ruptured Pipes Or From Cracked Large Pipes Which Actuates The Emergency Core Cooling System Single Rod Cluster Control Assembly Withdrawal At Full Power Major Reactor Coolant System Pipe Ruptures (Loss of Coolant Accident)

Major Secondary Systems Pipe Rupture Rupture of a Control Rod Drive Mechanism Housing (Rod Cluster Centrol Assembly Ejection) i BEAVER VALLEY - UNIT 1 3/4 1-19N AMENDMENT N0. 51 l

t

4 REACTIVITY C0flTROL SYSTEMS P_0 SIT 10tl ItiDICATI0ft SYSTEMS-0PERATIr1G LIMITIflG C0tiDITI0f1 FOR OPERATI0rl 3.1.3.2 The shutdown and control rod position indication system shall be OPERABLE as follows:

. Group Demand Counter (I), 1 per group

. Individual analog rod position instrument channel,1 per rod, + l'2 steps (l) accuracy

. Automatic Rod Position Deviation Monitor (2), setpoints 5 12 steps (1) During the first hour during and following rod motion, the group demand counter is the primary indicator of precise rod position information, with.the analog channels displaying general rod movement information. For power levels below 50%, a 1-hour thermal soak time is allowed before the analog channels are required, to perform within the specified accuracy.

(2) For power levels below 50% a one hour thermal soak time is allowed. Therefore, if a Rod Position Deviation Monitor alarm clears itself within this hour, the alarm is considered invalid.

~

l BEAVER VALLEY - UtilT 1 3/4 1-20 AMENDMENT NO. 51 l

L

lLIMfTfuGCCrJDITI0rtFOROPERATI0ri(continuedl APPLICABILITY: MODES 1 and 2*

ACTION:

If the Rod Position Indicating System indicates (2) a potentially a.

misalign ed rod (s), this indication shall be verified immediately (within 15 minutes) by measuring the analog rod position channel primary voltage.

If this meausrement c.onfirms that a rodsis misaligned, Specification 3.1.3.1.3,c is applicable.

b.

With a maximum of one group demand position indicator per bank inoperable either:

1.

Verify that all rod position indicators for the affected bank are OPERABLE and that the most withdrawn rod and the least withdrawn rod of the bank are within a maximum of 12 steps (indicated position) of each other at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , or 2.

Reduce THERMAL POWER to less than 50% of RATED THERIML POWER within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

c.

With a maximum of one analog rod position indicator per bank inoperable, either:

1.

Determine rod position for the affected rod by measuring the detector primary voltage, as follows:

a.

Immediately b.

If th.e associated rod moved greater than 6 steps (greater than 12 steps if all the rods in the group have been determined to be within 6 steps of group demand counter indicator by primary voltage measurements within the previous 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months )

At 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months intervals if the affected rod (s) are not fully inserted or c.

withdrawn d.

At 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months intervals if the affected rod (s)'are fully inserted or withdrawn, or, 2.

Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

d. With the Automatic Rod Deviation Monitor inoperable, POWER OPERATION may continue.. provided that the deviation between the indicated positions is checked by the operator at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . The provisions of Specification 3.0.4 are not applicable.

BEAVER VALLEY - UNIT 1 3/4 1-20a AMENDMENT NO. 51

- - - =

~

. SURVE!LLAriCE RE0VIREMEf1TS 4.1.3.2.1 Each of the group demand counters shall be determined to be OPERABLE by:

a.

Performing a CHAfifiEL CHECK by the group demand counters within a bank, and observing proper overlap of the indicated positions, at least once per 7 days; and b.

Performing a CHAtifiEL CHECK by an intercomparison between the control bank benchboard indicators and the logic solid state indicators in the logic cabinet, and determining their acreement within + 2 steps, at least once per 92 days.

4.1.3.2.2 Each of the analog rod position indicators shall be determined to be OPERABLE by:

a.

Performing a CHArittEL CHECK by intercompaison** between each analog rod position indicator and its corresponding group demand counter at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b.

Performing a CHAtiflEL FUtiCTI0t!AL TEST and CHAfitiEL CALIBRATIO!! at least once per 18 months.

4.1.3.2.3 The Automatic Rod Deviation Monitor shall be determined to be OPERABLE by performing a functional test at least once per 7 days, and the deviation between the position indicated by the individual analog rod position instrument channel and the position indicated by the corresponding group demand' counter shall be checked ** manually for each rod at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

For Core PHYSICS TESTItiG in Mode 2, primary detector voltage measurements may be used to determine the position of rods in shutdown banks A and B and control banks A and B for the purpose of satisfying Specification 3.1.3.2.

During Mode 2 operation, rod position indicators for shutdown banks A and B and control banks A and B may deviate from the group demand indicators by greater than + 12 steps during reactor startup and shutdown operations, while rods are being witWdrawn or inserted.

If the rod position indicators for shutdown banks A and B and control banks A and B deviate by greater than + 12 steps from the group demand indicator, rod withdrawiil or insertion may continue until the desired group height is achieved. When the desired group height is achieved, a one hour soak time is allowed below 50% reactor power to permit stabilization of the rod position analog indicators. To attain l

thermal equilibrium during the one hour soak time, the absolute value of rod motion shall not exceed 6 steps.

- For power levels below 50% one hour thermal " soak time" is permitted.. During i

this soak time, the absolute valve of rod motioa is limited to six steps.

l l

BEAVER VALLEY - UtJIT 1 3/4 1-20b AMEtiDMEt4T t10. 51

__..--.i_

. - _. =

.w

REACTIVITY C0!1 TROL SYSTEM POSITI0tl liiDICATION SYSTEM-SHUTDOWN LIMITIfiG C0!iDITI0tl FOR OPERATION 3.1.3.3. The group step demand counter and at least two analog rod position indication channels per group shall be OPERABLE for each group of shutdown or control rods not fully inserted.

APPLICABILITY: MODES 3*, 4*

and 5*

ACTION:

With less than the above required position indicator (s) OPERABLE, irmediately insert all rods or, immediately open the reactor trip system breakers.

SURVEILLANCE REOUIREMENTS 4.1.3.3 Each of the above required position indicator (s) shall be. determined to be OPERABLE by performance of Specifications 4.1.3.2.1 and 4.1.3.2.2.

With tne reactor trip system breakers in the closed position.

b BEAVER VALLEY - UNIT 1 3/4 l-21 AMENDMENT NO. 51

REACTIVITY CONTROL SYSTEMS R00 DROP TIME LIMITING CONDITION FOR OPERATION 3.1.3.4 The individual full length (shutdown and control) rod drop time from the fully withdrawn position shall be 4 2.2 seconds from beginning of decay of stationary gripper coil voltage to cashpot entry with:

8 a.

Tavg2: 541 F, and b.

All reactor coolant pumps operating.

APPLICABILITY: MODE 3.

ACTION:

a.

With the drop time of any full length rod determined to exceed the above limit, restore the rod drop time to within the above limit prior to proceeding to MODE 1 or 2.

b.

With the rod drop times within limits but determined with 2 reactor coolant pumps operating, operation may proceed provided THERMAL POWER is restricted to:

1.

<t 61% of RATED THERMAL POWER when the reactor coolant stop valves in The nonoperating loop are open, or

2. < 66% of RATED THERMAL POWER when the reactor coolant stop valves in the nonoperating loop are closed.

SURVEILLANCE REQUIREMENTS r

4.1.3.4 The rod drop time of full length rods shall be demonstrated through measurement prior to reactor criticality:

a.

For all rods following each removal of the reactor vessel head.

b.

For specifically affected individual rods following any maintenance on or modification to the control rod drive system which could affect the drop time of those specific rods, and c.

At least once per 18 months.

BEAVER VALLEY - UNIT 1 3/4 1-22 AMENDMENT NO. 51

...-.-.---...~...-.-------=.-.=-c e

REACTIVITY CONTROL SYSTEM SHUTDOWN R0D INSERTION LIMIT

. LIMITING CONDITION FOR OPERATION 3.1.3.5 All shutdown rods shall be fully withdrawn.

APPLICABILITY: MODES 1* and 2*#

ACTION:

With a maximum of one shutdown rod not fully withdrawn, except for surveillance testing pursuant to Specification (4.1.3.1.1), within one hour either:

a.

Fully withdraw the rod, or b.

Declare the rod to be inoperable and apply Specification (3.1.3.1).

SURVEILLANCE REQUIREMENTS 4.1.3.5 Each shutdown rod shcIl be determined to be fully withdrawn by use of the group demand counters, and verified by the analog rod position indicators **

a.

Within 15 minutes prior to withdrawal of any rods in control banks A, B, C or D during an approach to reactor criticality, and b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter.

5ee Special Test Exception 3.10.2 and 3.10.4

- For power levels below 50% one hour thermal " soak time" is permitted.

During this soak time, the absolute value of rod motion is limited to six steps.

With Keff 27 0

1 BEAVER VALLEY - UNIT 1 3/4 1-23 AMENDMENT N0. 51

REACTIVITY C0tlTROL SYSTEt45 00tlTROL ROD IriSERTI0tl lit 4ITS LIrilTIriG C0!lDITI0t1 FOR OPERATI0tt 3.1.3.6 The control banks shall be limited in physical insertion as shown in Figures 3.1-1 and 3.1-2.

APPLICABILITY: t40 DES 1* and 2*#

ACTI0ft:

With the control banks inserted beyond the above insertion limits, except for surveillance testing pursuant to Specification (4.1.3.1.1), either:

a.

Restore the control banks to within the linits within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , or b.

Reduce THER!iAL POWER within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to less than or equal to that fraction of RATED THERt4AL POWER which is allowed by the group position using the above figures, or c.

Be in at least HOT STAT;DBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLAf1CE REQUIREMEf1TS 4.1.3.6 When the Rod Insertion Limit tionitor is OPERABLE, the deviation between the position indicated by the individual analog rod position instrument channel and the position indicated by the corresponding group demand counter shall be checked **

manually for each roc.at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

When the Rod Insertion Limit Nonitor at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .noperable, the deviation bewteen Indicated positions shall i;e chec s

5ee Special Test Exception 3.10.2 and 3.10.3 iwith Keff 1.0

- For power} levels below 50%, one hour thermal " soak time" is permitted.0uring this soak time, the absolute valve of rod motion is limited to six steps.

BEAVER VALLEY - UtlIT 1 3/4 1-23 A AMErlDMEtlT t10. 51

=uw -

..a u.-

2 m :waa.ax. u.x yw e

GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION 3.10.2 The group neight, insertion and power distribution limits of Specifications 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.2.1, and 3.2.4 may be suspended during the performance of PHYSICS TESTS provided; a.

The THERMAL POWER is maintained.585% of RATED THERMAL POWER, and b.

The limits of Specifications 3.2.2 and 3.2.3 are maintained and determined at the frequencies specified in Specification 4.10.2.2 below.

APPLICABILITY: MODE 1 ACTION:

With any of the limits of Specifications 3.2.2 or 3.2.3 being exceeded while the requirements of Specifications 3.1. 3.1, 3.1. 3. 5, 3.1. 3. 6,

3.2.1, and 3.2.4 are suspended, either; a.

Reduce THERMAL POWER sufficient to satisfy the ACTION requirements of Specifications 3.2.2 and 3.2.3, or b.

lBe in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.10.2.1 The THERMAL POWER shall be determined to be 685% of RATED THERMAL POWER at least once per hour during PHYSICS TESTS.

i l

)

BEAVER VALLEY - UNIT 1 3/4 10 AMENDMENT N0. 51

't 1

.. - - ~ ~ ~ - - - - --..-.- - -.n _ _ _ _ =. - ~ ~a.

PHYSICS TESTS LIMITING CONDITION FOR OPERATION 3.10.4 The limitations of Specifications 3.1.1.4, 3.1.3.1, 3.1.3.5, and 3.1.3.6 may be suspended during the performance of PHYSICS TESTS provided; a.

The THERMAL POWER does not exceed 5% of RATED THERMAL POWER, and b.

The reactor trip setpoints'on the OPERABLE Intermediate and Power Range Nuclear Channels are set at625% of RATED THERMAL POWER.

APPLICABILITY: MODE 2.

ACTION:

With the THERMAL POWER >5% of RATED THERMAL POWER, immediately open the reactor trip breakers.

SURVEILLANCE REQUIREMENTS 4.10.4.1 The THERMAL POWER shall be determined to be.55% of RATED THERMAL. POWER at least once per hour during PHYSICS TESTS.

4.10.4.2 Each Intermediate and Power Range Channel shall be subjected to a CHANNEL FUNTIONAL TEST within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months prior to initiating PHYSICS TESTS.

4 i

BEAVER VALLEY - UNIT 1 3/4 10-6 AMENDMENT NO. 51

---en m --.,

7 e

.SASES 1

- y.i

..c_.4 3/4.1.2 BORATION SYSTEMS { continued)

The boration capability of either system is sufficient to provide a SHUT-00WN MARGIN from all operating conditions of 105 ak/lt after xenon decay and cooldown to 200"F.

The maximum boration capability requirements occur at EOL from full power equilibrium xenon conditions and requires 11,336' gallons of 7000 ppm borated water from the boric acid storage tanks or 49,917 gallons of 2000 ppm borated water from the refueling water storage tank.

WIth.the RCS temperature below 200"F, one injection system is acceptable

'without single fAllure consideration on the basis of the stable reactivity condition of the react'or and the additional restrictions prohibiting CORE ALTERATIONS and positive reactlyity change 19 the event the singl.e injection system becomes inoperable.

The boration capabillty required below 200*f j; d cooldown from 200'f tg sufficient to provide g SHUTDOWN MARGIN of 1% ak/k after xenon decay an This condition requires either 5000 gallons of,7000 ppe borated water from]$0'f, the-bsric acid storage tank 4 or 175,000 gallons of 2000 ppa borated yater from thp refueling water storage tank.

3/4.1.3 MOVABLE CONTROL ASSEM8 LIES,

/ -

The specifications of this section ensure that (1)' acceptable power distribution

.~"

lbnits are maintained, (2) the minimum SHUTDOWN NARGIN 15 maintained, and (3 the potential effects of rod misalignment on associated accident analyses are

< 0PERABILITY of the movable control assemblieg 13 established by obseryin9 roa action and detennining that rods are positioned gjthin i 12 steps (Indic'ated' position), of the respective group demand counter position.

TheOPERABILITY of the rod' position indication system is established'by appropriate periodic

~

2 CilANNEL CHECKS, CilANNEL FUNCTIONAL TESTS and CHANNEL CALIBRATIONS. OPERABILITY of the control rod position jndicatorg js' require 4 M determine control ' rod position and thereby ensure compliance ylth the control rod alignment and insertion limits. The OPERABLE condition for the analog rod position indicatorg ji defined as being capable of indicating rod position within i12 steps of the assbclated group demand in'dicator. For' power levels,below 50 percent, the specifications of this section permit a one hour stabilization period to permit stabiltzation of known thermal drif t in the analog rod position indicator channels.

During this stabilization period, greater reliance is placed upon the group demand position indicators to determine rod position. Above 50 eparcent power, rod motion is not expected to jnduce thermal transients of 1

' sufficient magnitude to exceed the rod position indicator instrument accuracy of + 12 steps. Limited use of rod position indication primary detector Voltages

'gs allowed as a backup method of determining control rod Positions. Comparison Pf the group demand indicator to the calibration curve is sufficient to allow

. d2 termination that a control rod is indeed rnisaligned from jts bank when primary 1' voltage measurements are used.

Comparison of the group demand counters to the i bank insertion ilmits with yerification of rod position with the analog rod SEAVER VALLE't - U' LIT ' 1 B 3/4 1-3

' AMENDMENT'NO. 51 s E e

--_-._y...._-...m.

.,..,._._o_

... - m-.

REACTIVITY CONTROL SYSTEMS BASES position indicators (after thermal soak after rod motion) is sufficient i

j verification that the control rods are above the insertion limits below 50 i

percent power.

Above 50 percent pcwer, reliance is placed on the analog rod i

position indicator channels to assure that control rods are above the insertion limits.

The ACTION statements which permit limited variations from the basic requirements are accompanied by additional restrictions which ensure that the 1

original design criteria are met.

Misalignment of a rod requires measurement of peaking factors and a restriction in THERMAL POWER. These restrictions provide assurance of fuel rod integrity during continued operation.

In addition, those safety analyses affected by a misaligned rod are reevaluated to confirm,

that the results remain valid during future operation.

l i

Continuous monitoring of rod position with respect to insertion limits and i

rod deviation is provided by the rod insertion limit monitor and rod deviation I

monitor, respectively.

OPERABILITY of the rod deviation monitor is verified

{

by a functional test at least once per 7 days and by compairson of the indicated analog positions versus the respective group demand counters at least i

l once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

If the rod deviation monitor or the rod insertion limit monitor is Ifl0PERABLE, the frequency of manual comparison of indicated rod position is increased to an interval of at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

I i

l i

i i

I l

t I

l I

i 3EAVER VALLEY - UNIT 1 B 3/4 1-4 AMENDMENT f;0. 51

p0WER DISTRI3UTION LIMITS

,m BASES An evaluation of DN3 and test data froc experimen:s of fuel rod bowing in subchannels containing th1=ble cells has identified tha 1: is appropriate to i= pose a penalty factor to the accident analyses DN3R results. Accordingly, a thimble cell red bow penalty as a function of f uel burnup, is applied to the ceasured values of the enthalpy rise hot channel factor, F'4 Additional in-La_.

plan: operational data and DN3 tests designed to quantify the effects of rod bow have provided a basis for reducing the penalty applied to the en:halpy rise ho channel factor to account for rod bow effects.

The necessary penalty is applied as a functica of fuel burnup (See Figure 3.2-3).

The radial peaking fac:c F,

( ) is =easured periodically to provide assurance that the ho: channel factor, FQ (Z), re=ains within its 11:1:.

The F 11=1; for X7 Rated Ther=al Power ( y p) as provided in the Radial Peaking Factor Lini: Report y

per specifica:1en 6.9.1.10 was deter =ined fro = expected power con:rol =aneuvers 4

over the full range of burnup conditions in the core.

3/4.2./. OUADPANT POWER TILT R.CIO The quadran: power til: ratic lici: assures tha: the radial power' distribution satisfies :he design values used in the power capability analysis.

Radial power distribution =easure=ents are =ade during startup testing and periodically during power opera: ion.

The 11:1: of 1.02 a: which corree:1ve action is required provides DN3 and linear heat generation rate protection with x-y plane power tilts.

The tvo hour :1=e allowance for operation with a til: condition greater than l

1.02 but less than 1.09 is provided to allow ident!.fication and correction of a dropped or =isaligned rod.

In the event such action does not correct the til:

the cargin for uncertain'ty on F is reinstated by reducing the caximum allowed, q

power by 3 percen: for each percent of tilt in excess of 1.0.

SE AVE R V ALLEY-U NIT 1 33/4 2-3 AMENDMENT N0. 51

_, _ ~. _

I POWER DISTRIBUTION LIMITS SURVF.ILLANCE REQUIREMENTS (Continued) b) At least once per 31 EFFD, whichever occurs first.

2.

When the F is less than or equal to the F li=it for theappropYlate=easuredcoreplane,adgitiEnalpower distribution =aps shall be taken and F at least once per 31 EFP3? co= pared to RI? and F L Fxy X7 RT^S e.

The F li=it for Rated Ther=al Power (FX7 ) shall be provided x7 for all core planes containing bank "D" control rods and all unrodded core planes in a Radial Peaking Factor L1=it Report per specification 6.9.1.10.

f.

The F limits of e, above, are not applicable in the following X7 core plane regions as =easured in percent of core height fro = the botto= of the fuel:

1.

Lower core region fro = 0 to 15*, inclusive.

2.

Upper core region fro = 85 to 100% inclusive.

3.

Grid plane regions at 17.8 I 2%, 32.1 ! 2%,

46.4 t 22, 60.6 i 2% and 74.9

22, inclusive 4.

Core plane regions within i 2% of core height (i 2.88 inches) about the bank de=and position of the bank "D" control rods.

C L

g.

With F exceeding Fg, the effects of F Q (Z) shall be.

on F rf g

evaluated to deter =ine if F (Z) is within its li=1t.

~

4.2.2.3 When F (Z) is =easured pursuant to Specification 4.10.2.2, an over-all =easured F (Z) shall be obtained fro = a power distribution =ap and q

increased by 3 to account for =anufacturing tolerances and further increased by 5% to account for =easure=ent uncertainty.

BEAVER V ALL EY-U NIT 1 3/4 2-6a AMENDMENT N0. 51

9

?OWER DISTRIBUTION LIMITS N

m NUCLEAR INTHALPY ECT CHANNEL FACTOR -

F' H A

LIMITING CONDITION FOR OPERATION i

3.2.3 F'N shall be 11=ited by the following relationship:

~

E

_y gg 5 1.55 [1 + 0.2 (1-?)]

ri_R3p(3g))

i where ? = ~EERMAL PCk*ER RATED TEE?#.AL POWER RSP (EU) = Rod Bow Penalty as a function of region average burnup as shown in Figure 3.2-4, where a region is defined as those assenblies with the sane loading date (reloads) or enrichnen: (first cores).

APPLICA3ILITY:

MODE 1 ACTION:

With F;N exceeding 1:s 11:1 :

u A

a. Reduce ~EE?SX POWER to less than 50* of Pa!ED TdEPSE POWER within 1

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and reduce the Power Range Neutron Flux-Eigh Trip Se: points to 5 55* of RA~ED THER."X POWER vithin the nex: 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , i

N

b. De=enstrateL thru in-core napping that F'., is within 1:s 11=it within An 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after exceeding the 11:1: or reduce THE??X POWER to less l

than 5: of ?.ATED TdERMAL P0k'IR within the nex: 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , and

c. Identify and correc: the cause of the out of 11=1; cendition p: Lor to increasing ~EI??X POWER; subsequen: P0k'IR OPE?a!!ON =ay proceed l

N provided that F'3 is denenstrated through in-core napping to be with-A in its.ti=1: at a nociaal 50% of RATED THEFFE POWER prio: to exceeding this THERMAL P0k'ER, at a no=inal 75* of RA~ED ~EE?S.AL POWER prio to exceeding this THEF?.AL power and within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after attaining 95: ir greater RATED THE??.AL P0k'FR.

4 BEAVER V ALLEY-U NIT 1 3/4 2-8 AMENDMENT N0. 51

5 3

y_

_ _2

- 0 _ _

e 0

2. /_

_ _0

- t

)

1 7

__/

_ _ 0,

_ /

n 2

0 0

/

_3

_/ _ _

3 0,

3

_ f_ f_ _

_ _/ _

3 3

_ eg_

(

_ 0 0

0

_t

/

0,l P

U

4. I N

5

_i 26

_u __ _

2 R

U

_ _ / (2I B

l

)

F U

O

)

T 0, _-

M N

/

O 6

D I

_ _ 5 W

T 7

0 H

C 2 3 4 N 1

0

- U 2

1 F

2

(

3 A EC e S R

u A

r A E

g Y V

i T 5

A F L N

N 1

A O

E I

P G

E W

R O

B D

O 0

R 1

5 0

5 4

3 2

1 0

0 0

0 gm ga<gm aOm cE a!

wggw ygs,

~a H y~ erF ggoh4 =o. $

t

... l, ADMINISTRATIVE CONTROLS i.

Performance of structures, systems, or components that requires

~

remedial action or corrective measures to prevent operation in a manner less conservative than that assumed in the accident analyses in the safety analysis report or technical specifications bases; or discovery during plant life of conditions not specifically considered in the safety analysis report or technical specifications that require remedial action or corrective measures to prevent the existence or development of an unsafe condition.

THIRTY-DAY WRITTEN REPORT 6.9.1.9 The types of events listed below shall be the subject of written reports to the Director of the Regional Office within 30 days of occurrence of the event.

The written report shall include, as a minimum, a completed copy of a licensee event report form.

Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide ccmplete explaqation of the circumstances surrounding the event.

Reactor protection system of engineered safety feature instrument settings a.

which are found to be less conservative than those established by the technical specifications but which do not prevent the fulfillment of the functional requirements of affected systems.

b..

Conditions leading to operation in a degraded mode permitted by a limiting condition for operation or plant shutdown required by a limiting condition for operation, Observed inadequacies in the implementation of administrative or procedural c.

controls which tnreaten to cause reduction of degree of redundancy pro-vided in reactor protection systems or engineered safety feature systems.

d.

Abnormal degradation of systems other than those specified in 6.9.1.8.c above, designed to contain radioactive material resulting from the fission process.

RADIAL PEAKING FACTOR LIMIT REPORT 6.9.1.10 The F limit for Rated Thermal Power (F shall be -rovided to the xy Director of the Regional Office of Inspection and Enforcement, with a ' copy to the Director, Nuclear Reactor Regulation, Attention Chief of the Core Performance Branch, U. S. Nuclear Regulatory Commission, Washington, DC 20555 for all core planes containing bank "D" control rods and all unrodded core planes at least 60 days prior to cycle initial criticality.

In the event that the limit would be submitted at some other time during core life, it will be submitted 60 days iBEAVER V ALLEY-U NIT 1 6-16 AMENDMENT N0. 51

ADMINISTRATIVE CONTROLS prior to the date the limit would become effective unless otherwise exempted by the Commission.

RP Any information needed to support F will be by request from the NRC and need not be included in this report.

SpECIAL REPORTS 6.9.2 Special reports shall be submitted to the Director of the Office of Inspection and Enforcement Regional Office within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:

a.

Inservice Inspection Program Reviews, Specifications 4.4.10.1 and 4.4.10.2.

b.

ECCS Actuation, Specifications 3.5.2 and 3.5.3.

c.

Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.

d.

Inoperable Meteorological Monitoring Instrumentation, Specifi-cation 3.3.3.4.

e.

Seismic event analysis, Specification 4.3.3.3.2.

f.

Sealed source leakage in excess of limits, Specification 4.7.9.1.3.

g.

Fire Detection Instrumentation, Specification 3.3.3.6.

h.

Fire Suppression Systems, Specification 3.7.14.1, 3.7.14.2, and 3.7.14.3.

6.10 RECORD RETENTION 6.10.1 The following records shall be retained for at least five years:

a.

Records and logs of facility operation covering time interval at each power level.

~

b.

Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.

c.

All REPORTABLE OCCURRENCES submitted to the Commission.

d.

Records of surveillance activities, inspections and calibrations required by these Technical Specifications.

BEAVER V ALLEY-U NIT 1 6-17 AMENDMENT N0. 51

-

ML20054J438

Text

Attachment:

Navigation menu

Search