B13314, Proposed Tech Specs 1.37,3/4.3.1,3.3.3.9,3/4 9.2,Bases 2.2.1,3/4.3.3.9 & 3/4.3.4 & Tables 2.2-1,3.3-1,3.3-1a,4.3-1, 3.3-2,4.3-2,3.3-7 & 4.3-6 Re Reactor Protection Sys & Nuclear Instrumentation Sys

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Proposed Tech Specs 1.37,3/4.3.1,3.3.3.9,3/4 9.2,Bases 2.2.1,3/4.3.3.9 & 3/4.3.4 & Tables 2.2-1,3.3-1,3.3-1a,4.3-1, 3.3-2,4.3-2,3.3-7 & 4.3-6 Re Reactor Protection Sys & Nuclear Instrumentation Sys
ML20248C410
Person / Time
Site: Haddam Neck, 05000216  File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 07/28/1989
From:
CONNECTICUT YANKEE ATOMIC POWER CO.
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Shared Package
ML20248C406 List:
References
B13314, NUDOCS 8908100006
Download: ML20248C410 (22)
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r Attachment No. 1 Haddam Neck Plant Description of Proposed Technical Specification Changes.

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July 1989

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1. Attachment 1 B13314/Page 1

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Haddam Neck Plant if Description of Proposeu Technical Specification Chanagi Section Iitig EAgg Description I. Reactor Protection System (RPS) l.0 Definitions - RTS Response 1-7 Add a new definition.

Time 3.3.1 RTS Instrumentation 3/4 3-1 Reference response time table in LCO. Add new surveillance requirement for response times.

Table 3.3-1 RTS Instrumentation '3/4 3-2 Changes to reflect the increase in numbers of channels per loop (based'on plant upgrades).

Table 3.3-la RTS Inst. Response Time 3/4 3-7a New table providing RTS instrumentation response times.

Table 4.3-1 RTS Inst. Sur. Req. 3/4 3-8 Change "RC Flow-low" analog channel operational test from Note "7" to "SW" - (meaning "once per 42 days").

Table 4.3-1 Table Notations 3/4 3-11 Delete Note "7".

l Table 3.3-2 ESF Actuation Sys. Inst. 3/4 3-13 Change " Containment Pressure--

High" numbers for channels to reflect plant upgrades; add footnote 24.

Table 3.3-2 ESF Actuation Sys. Inst. 3/4 3-15 Change " Containment Pressure -

High" numbers for channels to reflect plant upgrades; adjust l

footnote to "20, 24".

l Table 4.3-2 ESF Actuation Syst. Inst. Change " Containment Pressure -

3/4 3.-20

' High" analog channel

' operational test from "R" to "SW".

Table 4.3-2 ESF Actuation Syst. Inst. 3/4 3-22 Change " Containment Pressure -

High" analog channel operational test from "R" to "SW," .

l

". A'ttachment 1

'B13314/Page.2-Section Title Egge Description III.' Nuclear Instrumentation System (NIS)

Table 2.2-1 RTS Inst. Trip Setpoints 2-5 Revise the list of trip setpoints/ allowable. values to reflect plant upgrades;-

change title of " Intermediate Range" to " Wide Range" to reflect plant upgrades.

Bases 2.2.1 RTS Inst. Setpoints B2-3 Reflect the changes' made to Table 2.2-1.

-Table 3.3-1 RTS Instrumentation 3/4 3-2 Change wording to reflect plant upgrades that provide a more flexible " overpower trip";

change wording to reflect the new " Wide Range" neutron monitors; adjust " modes" and

" actions."

Table 4.3-1 RTS Instrumentation 3/4 3-8 Change wording to reflect plant upgrades.that provide a more flexible " overpower trip";

increase test frequencies,'

change test modes;'one test frequency was relaxed (based on manufacturers recommenda-tion); change wording to reflect the ~ new " wide range" neutron monitors; increase test f aquency.

3.3.3.9 Boron Dilution Alarm 3/4 3-53a Provides new LCOs and SRs for

~2 shutdown monitors.

Bases 3/4.3.3.9 Boron Dilution Alarm B3/4 3-5 Provides discussion of new Section 3.3.3.9.

Table 3.3-7 Accident Monitoring 3/4 3-35 Add a new section for the Instrumentation " wide range nuclear instrumentation" to reflect plant upgrades.

Table 4.3-6 Accident Monitoring 3/4 3-39 Add a new SR for the " wide Instrumentation range nuclear instrumentation" to reflect plant upgrades.

3.9.2 Refueling 0;ierations - 3/4 9-2 Add an LCO to address Instrumentation operability of the " Source Range High Neutron Level Alarms."

9 '

Docket No. 50-2J3 B13314 b

Attachment No. 2 Haddam Neck Plant Proposed Technical Specifications Changes Revised Pages 1

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July 1989  !

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iw i: DEFINITIONS'

- REACTOR' TRIP SYSTEM RESPONSE ' TIME 1:

1.37 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the' t-ime intarval fro

'> when the monitored parameter exceeds its Trip Setpoint at the channel sensor until actuation signal output to the Reactor Trip breakers.

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HADDAM NECK 17

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IABLE 1,1

.s FRE0VENCY NOTATION NOTATION FRE00ENCY S

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

D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

W At least once per 7 days.

B At least once per 14 days.

M At least once per 31 days.

SW t

At least once.per 42 days, Q At least once per 92 days.

SA At least once per 184 days. ,

R At least once per 18 months.

S/U Prior to each reactor criticality.

P Prior to each release.

N.A. Not applicable.

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J 3/4.3 INSTRUMENTATION

- 2/_L3 1 REACTOR TRIP SYSTEM INSTRUMENTATION l

LIMITING CONDITION FOR OPERATION 3'3.1 As a minimum, the Reactor Trip System instrumentation channels and interlocks of Table 3.3-1 shall be OPERABLE with response times as shown in Table 3.3-la.

APPLICABILITY: As shown in Table 3.3-1.

ACTION: As shown.in Table 3.3-1.

SURVEILLANCE RE0VIFEMENTS j

4.3.1.1 Each Reactor Trip System instrumentation channel and interlock logic shall be demonstrated OPERABLE by the performance of the Reactor Trip System Instrumentation Surveillance Requirements specified in Table 4.3-1.

4.3.1.2 The REACTOR TRIP SYSTEM RESPONSE TIME of each Reactor trip function once shall per 18 be demonstrated to be within its limit at least months.

Each test shall include at least one train such that both trains are tested at least once per 36 months and one channel per function such that all channels are tested at

-least once every N times 18 months where N is the total number of .

redundant channels in a specific Reactor trip function as shown in the " Total No. of Channels" column of--Table 3.3-1.

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REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIME FUNCTIONAL UNIT REACTOR TRIP SYSTEM RESPONSE TIME Power Range Nuclear Flux 0.5 sec.*

Low-Pressure-Reactor. Trip < 1.35 sec.**

(VLPS)

High Pressure Reactor Trip < 1.35 sec.

Start-Up Rate Reactor Trip '~

< 1.0 sec.*

Pressurizer Level < 1.35 sec.

Reactor Trip Low-Flow Reactor Trip ~ < 1.85 sec.

(Flow Channel)-

Safety Injection Reactor Trip < 1.35 sec.

(Pressure Low)

I Neutron detectors are exempt from response time te' sting. Response time of the neutron flux signal portion of the channel shall be measured y- from detector output or input of first electronic component in channel.

RTD response time is not included in this acceptance criteria.

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TABLE NOTATIONS With the Reactor Trip System breakers in the closed position and the Control Rod Drive System capable of rod withdrawal.

(a) THERMAL POWER above 10% of RATED THERMAL POWER.

(b) THERMAL POWER 1 74% of RATED THERMAL POWER.

(c) THERMAL POWER above 10% but below 74% of RATED THERMAL POWER.

(d) THERMAL POWER below 10% of RATED THERMAL POWER.-

(1) If not performed in previous 31 days.

(2) Comparison of calorimetric to excore power indication above 15% of RATED THERMAL POWER. Adjust excore channel gains consistent with calorimetric power if absolute difference is greater than 2%. The provisions of Specification 4.0.4. are not applicable for entry into MODES 1 or 2.

This requirement is not applicable when the Power Range Channels have had their gains adjusted to maintain the 9% trip margin for steady state cond'itions at power levels other than 16%, 65%, and 100% RATED THERMAL POWER. When this exception is used, a heat balance calculation will continue to be performed on a daily basis to determine core power, and the power range channels will be verified daily to be 9% below the selected overpower trip setpoint.

(3) Neutron detectors may be excluded from CHANNEL CALIBRATION.

(4) The TRIP ACTUATING DEVICE OPERATIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip System breakers.

-(5) Following a refueling outage, the calibration is performed subsequent to the plant reaching RTP. The provisions of Specification 4.0.4 are not applicable.

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INSTRUMENTATION' 7 BORON DILUTION ALARM LIMITING CONDITION FOR OPERATION 3.3.3.9 Two Shutdown Monitors will be operable with the Alarm setpoints set at or below 2.00 times the steady state level.

APPLICABILITY Modes 3, 4, 5, a.id 6 ACTION:

With the Boron Dilution Alarm system inoperable, except for surveillance testing:

a. Initiate continuous monitoring of the Source Range Channels or
b. Realign tne Chemical and Volume Control System (CVCS) to preclude the possibility of an inadvertent Boron Dilution event.

SURVEILLANCE REQUIREMENTS 4.3.3.9.1 The operability of the Shutdown Monitors shall be demonstrated once per Month when the Reactor is in Modes 3, 4, 5, or 6.

i HADDAM NECK 3/4 3-54 I

' REFUELING OPERATIONS l

3/4 9.2 INSTRUMENTATION l' LIMITING CONDITION FOR OPERATION I

3.9.2.a As a minimum, two Source Range Neutron Flux Monitors shall be OPERABLE and operating, each with continuous visual indication in the control room and one with audible indication in the containment and control room when CORE ALTERATIONS or positive reactivity changes are taking place.

When CORE ALTERATIONS or p3sitive reactivity changes are not taking place, at least one Source Range Neutron Flux Monitor shall.be OPERABLE and

, operating with a visual iadication in the control room and audible l

indication in the contair. ment.

I 3.9.2.b As a minimum, two Source Range High Neutron Level Alarms (Containment Evacuation). shall be OPERABLE ard operating with a minimum logic to audibly alarm in both the control room and containment of one (1) of two (2).

APPLICABILITY: MODE 6.

ACTION:

a. With less than the required monitors operable or operating, determine the boron concentration of the Reactor Coolant Syctem at

' east once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SURVEILLANCE k34IREMENTS 4.9.2 Each Source Range Neutron Flux Monitor shall be demonstrated OPERABLE by performance of:

a. A CHANNEL CHECK 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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b. An ANALOG CHANNEL OPERATIONAL TEST within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to the initial start of CORE ALTERATIONS, and
c. An ANALOG CHANNEL OPERATIONAL TEST at least once per 7 days.

1 HADDAM NECK 3/4 9-2 l

l

\= s b* R LIMITING SAFETY SYSTEM SETTINGS ld' BASES l

2.2.1 REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS The Reactor Trip Setpoint Limits specified in Table 2.2-1 have been selected l

to ensure that the reactor core and Reactor Coolant System are prevented from exceeding their acceptance criteria during normal operation and' design i

basis anticipated operational occurrences and to assist the Engineered l Safety Features Actuation System in mitigating the consequences of

! accidents. Operation with a trip set less conservative than its Trip l

Setpoint but within its specified Allowable Value.is acceptable on the basis that the ' difference between each Trip Setpoint and the Allowable Value'is equal to or less than a drift allowance accounted for in the design basis analysis.

The various Reactor trip circuits automatically open the Reactor trip breakers whenever a condition monitored by the Reactor Trip System reaches a preset or calculated level. The Reactor Trip System initiates a Turbine trip signal whenever Reactor trip is initiated. .This prcvents the reactivity insertion that would otherwise result from excessive Reactor Coolant System cooldown and thus avoids unnecessary actuation of the Engineered Safety Features Actuation System.

Manual Reactor Trio The Reactor Trip System includes manual Reactor trip capability.

Egwer Ranae. Neutron Flux The Power Range Neutron Flux trip provides core protection against rapid reactivity excursions. In order to provide protection over the entire i operating range, the trip function has ten (10) d.ifferent setpoints. The I trip is credited in the following design basis events; steam line break, i control rod ejection, excess steam flow, control rod withdrawal and isolated i loop startup. In order to reduce the time to trip for certain accidents  ;

occuring at low power, the overpower setpoint is incremented in 10% power intervals.

Wide Ranae. Neutron Flux )

The Wide Range, Neutron Flux, High Positive Rate trip provides core protection during reactor startup. This trip function provides protection for large reactivity insertion events initiated from a suberitical mode of l operation. This trip function is credited in the rod withdrawal from subcritical analysis.

I J

HADDAM NECK B2-3

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  • INSTRUMENTATION L

BASES

- ' 3/4.3.3.9 BORON DILUTION ALARM The. shutdown monitors provide indication of positive reactivity insertionTh during operation in Modes 3, 4.-5, and 6.

Boron Dilution design basis analysis.

, 3/a.3.4 FLOODING PROTECTION

- The liquid level instrumentation is provided to monitor liquid levels in-The system areas of potential flooding caused by local pipe ruptures.

ensures that early warning will occur so that protective action can be taken in the event of a localized flooding condition in areas of the plant that house safety-related equipment. As a result, the a degradation of flooding protection for any area. l in establishment the of a stage. .The establishment of frequent liquid level watch patro s affected areas is required to provide detection capability until the inoperable instrumentation is restored to OPERABILITY. f I

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