Text

Proposed Tech Specs,Allowing Testing of Individual Rod Position Indication Sys During Power Operation
	ML20033F555
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	03/14/1990
From:	; CONNECTICUT YANKEE ATOMIC POWER CO.
To:	;
Shared Package
ML20033F553	List: B13465, Application for Amend to License DPR-61,allowing Testing of Individual Rod Position Indication Sys During Power Operation of Plant; ML20033F555;
References
	NUDOCS 9003220028
	Download: ML20033F555 (10)
	v • d • e

-

_ _ _ _. _... _ ~

g,v.._

- ~,., _.

4 i

(5,p

-4.

i

, L,,:.

y;

-w

-.- ge

. 3 Y..

~.-

i g* :-..

p ::L, Docket No.'50-213'

).p B13465

,m l

4-M.

i i

y 1

i

-'5'

.t i

o j

C t

-?

it g

Attachment No. 1-1 Haddam Neck. Plant

.-(.

Proposed Changes to Technical Specifications j

L c

Reactivity Centrol Systems i

u i

t 3

?'

i i

, t t

l L'

i

.t i t t

l.

?

- 900322002s 90o334 fDR ADOCK 05000213

.I h

PDC i

sp l '.

F

p, March 1990 i

' i l

f 1,.

t l-n 1

l, r

..y m

y.~

y

.,...c-y

,w.

-,m..

-~- -.. =.. ---,,..,.,- - -,

....c+.- - -

_..-,n

.,,-,_*,m

I ~'

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS SECTION EA_qE 3/4.8.3 ONSITE POWER DISTRIBUTION 0perating...............................................

3/4 8-12 Shutdown................................................

3/4 8-14 3/4.9 REFUELING OPERATIONS i

3/4.9.1 BORON CONCENTRATION.....................................

3/4 9-1 3/4.9.2 INSTRUMENTATION.........................................

3/4 9-2 3/4.9.3 DECAY TIME..............................................

3/4 9-3 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS.......................

3/4 9-4 3/4.9.5 COMMUNICATIONS..........................................

3/4 9-5 3/4.9.6 MANIPULATOR CRANE.......................................

3/4 9-6 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING.........

3/4 9 7 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION High Water Level........................................

3/4 9-8 Low Water Leve1.........................................

3/4 9-9 3/4.9.9 CONTAINMENT PURGE SUPPLY, PURGE EXHAUST, AND PURGE EXHAUST BYPASS ISOLATION SYSTEM...................

3/4 9-10 3/4 9.10 WATER LEVEL - REACTOR VESSEL.............................

3/4 9-11 3/4.9.11 WATER LEVEL-STORAGE P00L................................

3/4 9-12 3/4.9.12 FUEL STORAGE BUILDING AIR CLEANUP SYSTEM................

3/49-13 i

l 3/4.10 SPECIAL TEST EXCEPTIONS o

1 3/4.10.1 SHUTDOWN MARGIN.........................................

3/4 10-1 1

L 3/4.10.2-PHYSICS TESTS...........................................

3/4 10-2

~3/4.10.3 POSITION INDICATION SYSTEM - SHUTDOWN...................

3/4 10-3 3/4.10.4 POSITION INDICATION SYSTEM - OPERATING..................

3/4 10-4 l

l l

3/4.11 RADI0 ACTIVE EFFLUENTS l

l 3/4.11.1 LIQUID EFFLUENTS t

Concentration...........................................

3/4 11-1 i

Dose, Liquids...........................................

3/4 11-2 1

HADDAM NECK XI Amendment No. 125

4 p

v y

BASES i

j.

SECTION EAE 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 & 3/4.8.2 A.C. SOURCES, D.C. SOURCES, ONSITE POWER i

DISTRIBUTION............................................

B 3/4 8-1 3/4.9 REFUELING OPERATIONS 1

i L

3/4.9.1 BORON C0NCE.NTRATION.....................................

B 3/4 9-1 J

3/4.9.2 INSTRUMENTATION.........................................

B 3/4 9 1

+

3/4.9.3 DECAY TIME............

B 3/4 9-1 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS.......................

B 3/4 9-1 3/4.9.5 COMMUNICATIONS..........................................

B 3/4 9-1 3/4.9.6 MANIPULATOR CRANE.......................................

B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING..............

B 3/4 9-2

.i 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION...........

B 3/4 9-2

{

3/4.9.9 CONTAINMINT PURGE SUPPLY, PURGE EXHAUST, AND t

PURGE E.' qAUST BYPASS ISOLATION SYSTEM...................

B 3/4 9-2 t

3/4.9.10 & 3/4.9.11 WATER LEVEL - REACTOR VESSEL AND STORAGE P00L....................................................

B 3/4 9-3 3/4.9.12 FUEL STORAGE BUILDING AIR CLEANUP SYSTEM................

B 3/4 9-3 3/4.10 SPECIAL TEST EXCEPTIONS i

I 3/4.10.1 SHUTDOWN MARGIN.........................................

B3/410-1 3/4.10.2 PHYSICS TESTS...........................................

B 3/4 10-1 3/4.10.3 POSITION INDICATION SYSTEM-SHUTDOWN.....................

B 3/4 10-1 3/4.10.4 POSITION INDICATION SYSTEM - OPERATING..................

B 3/4 10-1 l

3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS........................................

B 3/4 11-1 3/4.11.2 GASE0US EFFLUENTS.......................................

B 3/4 11-2 l

3/4.11.3 TOTAL 00SE..............................................

B 3/4 11-3 l

l HADDAM NECK XV Amendment No. 125

~

\\

l REACTIVITY CONTROL SYSTEMS 3/4.1.3 MOVABLE CONTROL ASSEMBLIES BANK HEIGHT LIMITING CONDITION FOR OPERATION 1

3.1.3.1 All shutdown and control rods shall be OPERABLE and positioned within i 24 steps indicated position (RPI) of their bank position, as indicated by the average of the RPI for the respective bank.

]

APPLICABILITY: MODES 1* and 2*.

ACTION:

a.

With one or more 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 or Specification 3.1.1.4 is satisfied i

within I hour and be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With one rod trippable but inoperable due to causes other than addressed by ACTION a.,

above, or misaligned from its group position by more than 124 steps, POWER OPERATION may continue provided that within I hour:

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 bank with the inoperable rod are aligned to within 124 steps of the inoperable rod while maintaining the rod sequence and insertion limits provided in the TECHNICAL REPORT SUPPORTING CYCLE OPERATION.

The THERMAL POWER Level shall be restricted pursuant to Specification 3.1.3.6.1 during subsequent four loop operation or Specification 3.1.3.6.2 during subsequent three loop operation, or 3.

The rod is declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 for four loop operation or Specification 3.1.1.4 for three loop operation is satisfied.

POWER OPERATION may then continue provided that:

a)

The THERMAL POWER level is reduced to less than or equal to 65% of RATED THERMAL POWER within the next hour and within the following 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the Nuclear Overpower Trip Setpoint is reduced to less than or equal to 72% of RATED THERMAL POWER.

b)

The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 for four loop operation or Specification 3.1.1.4 for three loop operation is determined at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ; i

See Special Test Exceptions Specifications 3.10.2 and 3.10.4.

l HADDAM NECK 3/4 1-18

REACTIVITY CONTROL SYSTEMS POSITION INDICATION SYSTEMS 0PERATING LIMITING CONDITION FOR OPERATION 3.1.3.2 The Group Position Indication System (group step counters) and the Individual Rod Position Indication System (IRPI) shall be OPERABLE and capable of determining the control rod positions within 16 steps.*

l APPLICABILITY: MODES 1 and 2.

ACTION:

a.

With a maximum of one individual rod position indicator per bank inoperable, restrict the movement of the rod group which includes the nonindicating rod to i 8 steps from the position last determined prior to loss of the nonindicating rod.

If the position of the nonindicating rod is not determined within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , declare the rod inoperable and refer to Specification 3.1.3.1.

b.

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

1.

Verify that all _ individual 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 32 steps 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.

With four loops operating, reduce THERMAL POWER to less than 65% of RATED THERMAL POWER within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , or 3.

With three loops operating, reduce THERMAL POWER to less than 16% of RATED THERMAL POWER within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

c.

With more than one individual rod position indicator or group rod position indicator per bank inoperable, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months with the reactor trip breakers open or the control rod drive lift coils deenergized.

SURVEILLANCE RE0VIREMENTS 4.1.3.2 Each group and individual rod position indicator shall be determined to be OPERABLE by verifying that the bank average individual rod position and the group rod position agree within 16 steps at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when the rod position deviation monitor is inoperable, then compare the individual rod position and the group rod position at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

See Special Test Exceptions Specification 3.10.4.

HADDAM NECK 3/4 1-21

REACTIVITY CONTROL SYSTEMS SHUTDOWN ROD INSERTION LIMIT 4

LIMITING CONDITION FOR OPERATION 3.1.3.5 All shutdown rods shall be withdrawn to equal to or greater than 317 steps.

APPLICABILITY: MODES 1* and 2* **.

ACTION:

With a maximum of one shutdown rod not fully withdrawn, ex:ept for surveillance testing pursuant to Soecification 4.1.3.1.2, within I hour either:

a.

Fully withdraw the shutdown rod, or

b..

3.1.3.1.

Declare the shutdown rod to be inoperable and apply Specification SVRVEILLANCE RE0VIREMENTS 4.1.3.5 Each shutdown rod shall be determined to be fully withdrawn:

a.

Within 15 minutes prior to withdrawal of any rods in Control Bank A or B during an approach to reactor criticality, and b.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

t l

l See Special Test Exceptions Specifications 3.10.2 and 3.10.4.

With K,ff greater than or equal to 1.

l-L HADDAM NECK 3/4 1-24 1

l..

REACTIVITY CONTROL SYSTEMS i

CONTROL GROUP INSERTION LIMITS FOUR LOOPS OPERATING LIMITING CONDITION FOR OPERATION a

3.1.3.6.1 The control banks shall be limited in physical insertion as shown in the TECHNICAL REPORT SUPPORTING CYCLE OPERATION.

1 APPLICABILITY: MODES 1* and 2* ** (Four Loop Operation).

ACTION:

With the control banks inserted beyond the above insertion limits, except for surveillance testing pursuant to Specification 4.1.3.1.2:

i a.

Immediately initiate action to restore the control banks to within the limits within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , or b.

Immediately initiate action to reduce THERMAL 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 THERMAL POWER which is allowed by the bank position using the above figure, or i

c.

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

i L

SURVEILLANCE RE0VIREMERTS 4.1.3.6.1 The position of each control bank shall be determined to be l

within the insertion limits at least once per_12 hours by verifying the individual rod positions.

l l

l See Special Test Exceptions Specifications 3.10.2 and 3.10.4.

l With K,ff greater than or equal to 1.

HADDAN NECK 3/4 1-25--

REACTIVITY CONTROL SYSTEMS CONTROL GROUP INSERTION LIMI*S THREE LOOPS OPERATING LIMITING CONDITION FOR OPERATION 3.1.3.6.2 The control banks shall be limited in physical insertion as shown in the TECHNICAL REPORT SUPPORTING CYCLE OPERATION.

APPLICABILITY: MODES 1* and 2* ** (Three Loop Operation).

A.CTION:

With the control banks inserted beyond the above insertion limits, except for surveillance testing pursuant to Specification 4.1.3.1.2:

a.

Immediately initiate action to restore the control banks to within the limits within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , or r

b.

Immediately initiate action to reduce THERMAL 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 THERMAL POWER which is allowed by the bank position using the above figure, or c.

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

SVRVEILLANCE RE0VIREMENTS 4.1.3.6.2 The position of each control bank shall be determined to be within the insertion limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying the individual rod positions.

See Special Test Exceptions Specifications 3.10.2 and 3.10.4.

With Keff greater than or equal to 1.

HADDAM NECK 3/4 1-26

=

C SPECIAL TEST EXCEPTIONS 3/4.10.4 POSITION INDICATION SYSTEM - OPERATING j

LIMITING CONDITION FOR OPERATION

]

l 3.10.4 The limitations of Specification 3.1.3.1, 3.1.3.2, 3.1.3.5, 3.1.3.6.1, and 3.1.3.6.2 may be suspended during testing of the Individual Rod i

Position Indication (IRPI) system provided:

a.

Each control rod in banks C, D and A is verified to be withdrawn to at least 317 steps within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to the start of the test.

b.

Banks C, D and A will not be moved during the test.

c.

The Group Position Indication (GPI) system is OPERABLE during the performance of the test.

APPLICABILITY:

MODES 1 and 2 during data collection / verification / adjustment testing of the Individual Rod Position Indication (IRPI) system.

)

Acl10H:

With any movement of banks C, D or A, terminate the test and restore the IRPI to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months with the reactor trip breakers open or the control rod drive lift coils de-energized.

SURVEILLANCE RE0VIREMENTS 4'.10.4

. Control rod banks C, D and A shall be verified to be fully withdrawn using the GPI system at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

l 1

HADDAM NECK 3/4 10-4

.q 3/4.10 SPECIAL TEST EXCEPTIONS i

BASES 3/4.10.1 SHUTDOWN MARGIN This Special Test Exception provides that a minimum amount of control rod worth is immediately available for reactivity control when tests are per-formed for control rod worth measurement.

This special test exception is required to permit the periodic verification of the actual versus predicted core reactivity condition occurring as a result of fuel burnup or fuel cycling operations.

3/4.10.2 PHYSICS TJ115 This Special Test Exception permits PHYSICS TESTS to be performed at less than or equal to 5% of RATED THERMAL POWER with the RCS T slightly lower than normally allowed so that the fundamental nuclear chare % eristics of the core and related instrumentation can be verified.

In order for various characteristics to be accurately measured, it is at times necessary to operate outside the normal restrictions of these Technical Specifications.

For instance, to measure the moderator temperature coefficient at BOL, it is necessary to position the various control rods at heights which may not normally be allowed by Specification 3.1.3.6 which in turn may cause the RCS T

to fall slightly below the minimum temperature of Specification 3ygg,4, a

3/4.10.3 POSITION INDICATION SYSTEM-SHUTDOWN This Special Test Exception permits the Position Indication Systems to be inoperable during rod drop time measurements.

The exception is required since the data necessary to determine the rod drop time are derived from the induced voltage in the position indicator coils as the rod is dropped.

This induced voltage is small compared to the normal voltage and, therefore, cannot be observed if the Position Indication Systems remain OPERABLE.

3/4.10.4 INDIVIDUAL R00 POSITION INDICA 1!0N SYSTEM - OPERATING l

This Special Test Exception permits the IRPI system to be inoperable during the performance of data collection / verification / adjustment testing of the i

IRPI.

The testing is required to develop and implement ' correction factors for each individual rod position indicator.

While the IRPI system is inoperable, the indicated individual rod position cannot be used to verify control rod alignment (Specification 3.1.3.1) or control rod insertion limits (Specifications 3.1.3.5, 3.1.3.6.1 and 3.1.3.6.2).

The actual rod l

l position for banks C, D and A is, however, unaffected by this testing.

I i

HADDAM NECK B3/4 10-1

ML20033F555

Text

Navigation menu

Search