ML20028H743

Proposed Tech Specs Re Digital Channel Operational Test

ML20028H743
Person / Time
Site:	Seabrook
Issue date:	01/24/1991
From:	PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:
Shared Package
ML20028H742	List: ML20028H741 ML20028H743
References
NUDOCS 9101290330
Download: ML20028H743 (12)

Text

.

New Hampshire Yankee January 24, 1991 ENCLOSURE 1 TO NYN-91010 PROPOSED TECHNICAL SPECIFICATION CH ANGES 9101290330 ADOCK910124 0500044,, s-PDR PDR p

l

___x.

'0EFINITIONS

) -..

CONTAINMENT INTEGRITY 1.7 CONTAINMENT INTEGRITY shall exist when:

y a. All penetrations required to be closed during accident conditions are either:

L Capable of being closed by an OPERABLE containment automatic 1) isolation valve system, or f

2) Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions.

b. All equipment hatches are closed and sealed,

c. Each air lock is in compliance with the requirements of $pecification i 3.6.1.3,

d. The containment leakage rates are within the limits of Specification 3.6.1.2, and-

e. The sealing mechanism associated with each penetration (e.g. , welds,

, bellows, or 0-rings) is OPERABLE.

CONTROLLED LEAKAGE 1.8 CONTROLLED LEAKAGE shall be that seal water flow supplied to the reactor coolant pump seals.

]

CORE ALTERATION 1.9 CORE ALTERATION shall be the movement or manipulation of any component within the reactor pressure m sel with the vessel head removed and fuel in the vessel. Suspension of CORE ALTERATION shall not preclude completion of L: movement of a component to a safe conarvative position.

DOSE EQUIVALENT I-131 L I I DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcurie / gram) which alone would-produce the same thyroid dose as the quantity and isotopic mixture of I-131, 1-132, 1-133, I-134, and 1-135 actually present. The thyroid dose conversion f actors used for this calculation shall be those listed in NRC 1 Regulatory Guide 1.109, Revision 1 " Calculation of Annual Doses to Man from j

Q Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I."

E - AVERAGE DISINTEGRATION ENERGY et 1.M - E shall be the average (weighted in proportion to the concentration of i

each radionuclide in the sample) of the sum of the average beta and gamma f energies per disintegration (MeV/d) for the radionuclides in the sample with .

half-lives greater than 10 minutes.

i l SEABROOK - UNIT 1 1-2 l

l

INSEllT POR TECHNICAL SPECIFICATION PAGE 12 DIGITAL CH ANNEL OPER ATIONAL TEST 1,10 A DIGITAL CHANNEL OPERATIONAL TEST shall consist of exercising the digital cornputer hardware using data bue manipulation and/or injecting simulated process data to verify OPERABILITY of alarm and/or trip functions.

I l

l

2 DEFINITIONS 3,

ENGINEERED SAFETY FEATURES RESPONSE TIME 3

1.it- The ENGINEERED SAFETY FEATURES (ESF) RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF Actuation Setpoint e at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.) Times shall include diesel generator starting and sequence loading delays where applicable.

FREQUENCY NOTATION

1. h The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.

GASEOUS RADWASTE TREATMENT SYSTEM T

1. R A GASEOUS RADWASTE TREATMENT SYSTEM shall be any system designed and

• installed to reduce radioactive gaseous effluents by collecting Reactor Coolant System offgases from the Reactor Coolant System and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

IDENTIFIED LEAKAGE a.

1. M IDENTIFIED LEAKAGE shall be:

a.

C4 Leakage (except CONTROLLED LEAKAGE) into closed systems, such as pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or

b. Leakage into the containment atmosphera from sources that are both specifically _ located and known either not to interfere with the operation of Leakage Detection Systems or not to be PRESSURE BOUNDARY LEAKAGE, or J

c. Reactor Coolant System leakage through a steam generator to the Secondary Coolant System.

MASTER RELAY TEST n

1.16 A MASTER RELAY TEST shall be the energization of each master relay and verification of OPERABILITY of each relay. The MASTER RELAY TEST shall include a continuity check of each associated slave relay.

MEMBER (S) 0F THE PUBLIC 66

- 1.9 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupa-tionally associated with the plant. This category does not include employees of the licensee, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries.

This category does include persons who use portions of the site for recre-ational, occupational, or other purposes not associated with the plant.

SEABROOK - UNIT 1 1-3

__. _ _ ~ _ . . - . _ _ _ . _ _ . _ _ _ _

l DEFINITIONS OFFSITE DOSE CALCULATION MANUAL 1.1hTheUFFSITEDOSECALCULATIONMANUAL(ODCM)shallcontaininPartAthe radiological effluent sampling and analysis program and radiological environ-

, mental monitoring program. Part B of the 00CM shall contain the methodology and parameters used in the calculation of offsite doses due to radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environ-

mental Radiological Monitoring Program.

OPERABLE - OPERABILITY

1. 5 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s),

and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s).

OPERATIONAL MODE - MODE 1.b An OPERATIONAL H0DE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.2.

PHYSICS TESTS u- -

1. W PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation:

(1) described in Chapter 14.0 of the FSAR, (2) authorized under the provisions of 10 CFR 50.59, or (3) otherwise approved by the Commission.

PRESSURE BOUNDARY LEAKAGE a3

1. M PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a nonisolable fault in a Reactor Coolant Syctem component body, pipe wall, or vessel wall.

PROCESS CONTROL PROGRAM v/

1.M The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, tests, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71 and r Federal and State Regulations, burial ground requirements, and other require-l ments governing the disposal of radioactive waste, l

PURGE - PURGING l

ar 1.f4' PURGE or PURGING shall be any controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

SEABROOK - UNIT 1 1-4

'OEFINITIONS U

glADRANTPOWERTILTRATIS u.

1.05 QUADRANT POWER TILT RATIO shall be the ratio of the maximum upper excore detector calibrated output to the average of the upper excore detector cali-brated outputs, or the ratio of the maximum lower excore detector calibrated 9

i output to the average of the lower excore detector calibrated outputs, whichever is greater. With one excore detector inoperable, the remaining three detectors shall be used for computing the average.

RATED THERMAL POWER 1.b RATED THERMAL POWER shall be a total reactor core heat the reactor coolant of 3411 MWt.

REACTORTRIP$YSTEMRESPONSETIM zb

1. 9 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its Trip Setpoint at the channel sensor until loss of stationary gripper coil voltage.

REPORTABLE EVENT

1. N A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 of 10 CFR Part 50.

CONTAINMENT ENCLOSURE BUILDING INTEGRITY ao i

1.99 CONTAINMENT ENCLOSURE BUILDING INTEGRITY shall exist when:

a. Each door in each access opening is closed except when the access opening is being used for normal transit entry and exit,

b. The Containment Enclosure Filtration System is OPERABLE, and

c. The sealing mechanism associated with each penetration (e.g., welds, bellows, or 0-rings) i; OPERABLE.

SHUT 00WN MARGIN

.s s

1. 3& SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is suberitical or would be subcritical from its present condition assuming all full-length rod cluster assemblies (shutdown and control) are fully inserted except for the single rod cluster assembly of highest reactivity worth which is assumed to be fully withdrawn.

-SITE B0UNDARY n.

1, M The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.

SEABROOK - UNIT 1 1-5

DEFINITIONS SLAVE RELAY TEST'

~

1. h A SLAVE RELAY TEST shall be the energization of each slave relay and verification of OPERABILITY of each relay. The SLAVE RELAY TEST shall include a continuity check, as a minimum, of associated testable actuation devices.

SOLIDIFICATION 4 J4

1. M SOLIDIFICATION shall be the conversion of wet wastes into a form that meets ship;.ing and burial ground requirements.

SOURCE CHECK af 1.9+ A SOURCE CHECK shall be the qualitative assessement of channel response when the channel sensor is exposed to a source of increased radioactivity.

STAGGERED TEST BASIS x

1.M A STAGGERED TEST BASIS shall consist of:

a. A test schedule for n' systems, subsystems, trains, or other designated components obtained by dividing the specified test interval into n equal subintervals, and

b. The-testing of one system, subsystem, train, or other designated j component at the beginning of each subinterval. -.

1 S

THERMAL POWER

1. b THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

TRIP ACTUATING DEVICE OPERATIONAL TEST f

JB 1.9P A TRIP ACTUATING DEVICE OPERATIONAL TEST shall consist of operating the Trip Actuating Device and verifying OPERABILITY of alarm, interlock and/or trip functions. The TRIP ACTUATING DEVICE OPERATIONAL TEST shall include adjustment, as necessary, of the Trip Actuating Device such that it actuates at the. required Setpoint within the required accuracy.

L UNIDENTIFIED LEAKAGE I. 1. UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE j or CONTROLLEO LEAKAGE.

UNRESTRICTED AREA I-

+o 1.M An UNRESTRICTED AREA shall be any area at or beyond the SITE B0UNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any f

area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.

SEABROOK - UNIT 1 1- 6 l

OEFINITIONS

.s VENTILATION un EXHAUST TREATMENT SYSTEM

1. 4&

A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system desig installed to reduce gaseous radiciodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal i adsorbers and/or HEPA filters for the purpose of removing iodines or particu-i lates from the gaseous exhaust stream prior to the release to the environment Such a system is not considered to have any effect on noble gas effluents .

Engineered Safety Features Atmespheric Cleanup Systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

VENTING VI 1.4t 3

confinement to maintain temperature, pressure, humidity, con provided or required during VENTING.other operating condition, is not in such a ma a VENTING process. Vent, used in system names, does not imply G

f SEABROOK - UNIT 1 1-7

TABLE 4.3-5 (Continued) 1 . , .

TABLE NOTATIONS s (1) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if the instrument indicates measured levels above the Alarm / Trip Setpoint, g

thoemstors<rverna n e tot

[. -

(2) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

(3) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made.

(4) CHANNEL CHECK shall consist of verifying indication of tank level during periods of release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

9 i b.

\

Q ..

7 i

ll l-i li l

SEABROOK - UNIT 1 3/4 3-59

._ ~ _

TABLE 4.3-6 (Continued)

TABLE NOTATIONS At all times.

• • During RADI0 ACTIVE WASTE GAS SYSTEM operation.

• • • When the gland seal exhauster is in operation.

[ **** The CHANNEL OPERATIONAL TEST for the flow rate monitor shall consist of I a verification that the Radiation Data Management System (ROMS) indicated flow is consistent with the operational status of the plant.

1. Noble Gas Monitor for_this release point is based on the main condenser air evacuation monitor.

(1) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if the instrument indicates measured levels above the Alarm / Trip Setpoint.

t no.i .c ser,%<, hs (2) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if the instrument indicates measured levels above the Alarm Setpoint.

t ..,,n.1. e w o.llau us t

- (3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall per-mit calibrating the system over its intended range of energy and measure-ment range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

(4) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

a. One volume percent oxygen, balance nitrogen, and

b. Four volume percent oxygen, balance nitrogen.

(5) The CHANNEL CALIBRATION shall be performed using sources of various activities covering the measurement range of the monitor to verify that the response is linear. Sources shall be used to verify the monitor response only for the intended energy range.

SEABROOK - UNIT 1 3/4 3-66

4 New Hampshire Yankee January 24, 1991 ENCLOSURE 2 TO NYN.91010 DESCRIPTION OF PROPOSED CHANGES

)

I-

44 DESCRIPTION OF PROPOSED CH ANGE Seabrook Station Technical Specification Tables 4.3 2, 4.3-3, 4.3 5, and 4.3 6 currently require the performance of a DIGITAL CHANNEL OPERATIONAL TEST for certain radiation monitoring instrumentation. This term is not currently defined in the Technical Specifientions and the requirement is therefore ambiguous. This proposed change adds a definition of a DIGITAL CHANNEL OPERATIONAL TEST to the Technical Specifications.

This proposed definition is based upon the equipment manufacturer's recommendations for functional testing of these radiation monitors. Additionally, three notes in Tables 4.3 5 and 4.3 6 are proposed to be revised to clarify the actual testing requirements.

SAFETY EVALUATION OF PROPOSED CHANGE

- New Hampshire Yankee has reviewed the proposed changes utilizing the criteria specified in 10CPR50.92 and has determined that the proposed changes would not

1. Involve a significant increase in the probability or consequences of an accident previously evaluated. The proposed change is a clarification of existing requirements, No change to any system, structure, or component is involved, _

nor are the criteria for determining the OPERABILITY of any component or system revised. The affected radiation monitors will continue to perform at the same functional level as currently required, with the same OPERABILITY requirements and allowed outage times. The proposed change does not affect the functional requirements of the affected systems. With these requirements unchanged, the potential doses to personnel onsite and members of the public are not increased.

2. Create the possibility of a new or different kind of accident from any accident previously evaluated. The proposed change clarifies testing requirements for existing plant equipment. This change does not alter the function of this equipment or create a new failure mode for this equipment. No changes to any plant equipment or operating procedures are involved.

3. Involve a significant reduction in a margin of safety, The proposed change adds a Technical Specification Definition of Digital Channel Operational Test (DCOT) and revises three notes in two Technical Specification Tables to clarify the intent of the Technical Specifications. The change does not affect the current method of performing the required surveillance testing. The proposed change does not affect the functional requirements of the affected systems.

The affected radiation monitors will continue to perform at the same functional level as currently required, with the same OPERABILITY requirements and allowed outage times. Therefore, the proposed change does not involve a

' reduction in a the margin of safety.

. --