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Amend 28 to License NPF-39,deleting Requirement That APRMs Be Operable When Plant Is in Cold Shutdown Condition & to Permit Snubber Surveillance to Be Performed When Unit Operating
	ML20245F862
Person / Time
Site:	Limerick
Issue date:	06/20/1989
From:	Butler W; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20245F865	List: ML20245F862; ML20245F866;
References
	NUDOCS 8906280271
	Download: ML20245F862 (22)
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NUCLEAR REGULATORY COMMISSION -

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PHILADELPHIA ELECTRIC COMPANY

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DOCKET NO. 50-352 LIMERICK GENERATING STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE i

1 Amendment No. 28 License No. NPF-39 1.

The Nuclear Regulatory Comission (the Comission) has found that A.

The application for amendment by Philadelphia Electric Company (the licensee) dated April 10, 1989, 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-cf.the Act, and the rules and regulations of the Comission; C.

1here is reasonable assurance (1) 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 Comission's regulations; D.

The iscuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.

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. NPF-39 is hereby amended to read as follows:

Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 28, are hereby incorporated into this licenso. Philadelphia Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

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4 FOR THE NUCLEAR REGULATORY COMMISSION-

/s/

Walter R. Butler, Director.

Project Directorate I-2 Division of Reactor Projects I/II n

Attachment-Changes to the Technica1L Specifica tions ~-

Date of Issuance:- June 20, 1980 I

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

FOR THE NUCLEAR REGULATORY. COMMISSION h

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Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II

Attachment:

' Changes to the Technical

-Specifications Date of. Issuance: June 20, 1989 9

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'll ATTACHMENT TO LICENSE AMENDMENT N0. 28

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c FACILITY OPERATING LICENSE N0. NPF-39 l

L DOCKET NO. 50-352 Replace the following pages of the Appendix A Technical Specifications with the attached page..The revised pages are identified by Amendment number and

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contain vertical lines indicating the area of change. Overleaf pages are provided to maintain document completeness.*

Remove Insert 3/4-3-1 3/4 3-1*

3/4.3-2 3/4 3-2 3/4 3-11 3/4 3-11 3/4 3-12 3/4 3-12*

3/4 3-17 3/4 3-17 3/4 3-18 3/4 3-18 3/4 3-23 3/4 3-23 3/4 3-24 3/4 3-24*

3/4 3-27 3/4 3-27 3/4 3-28 3/4 3-28*

3/4 4-9' 3/4 4-9 3/4 4-10 3/4 4-10*

3/4 6-57 3/4 6-57 3/4 6-58 3/4 6-58*

3/4 7-13 3/4 7-13 3/4 7-14 3/4 7-14*

6-5 6-5 6-6.

6-6*

__m__-__m_.________.____m___-m.

_.mm__

- 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION t

3.3.1 As a minimum, the reactor protection system instrumentation channels shown in Table 3.3.1-1 shall be OPERABLE with the REACTOR PROTECTION SYSTEM RESPONSE TIME as shown in Table 3.3.1-2.

APPLICABILITY:

As shown in Table 3.3.1-1.

ACTION:

a.

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for one trip syste.n, place the inoperable channel (s) and/or that trip system in the tripped condition

within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

The provisions of Specification 3.0.4 are not applicable.

b.

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for both trip systems, place at least one trip system ** in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and take the ACTION required by Table 3.3.1-1.

SURVEILLANCE REQUIREMENTS 9

4.3.1.1 Each reactor protection system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDIFIONS and at the frequencies shown in Table 4.3.1.1-1.

4.3.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 mor.ths.

4.3.1.3 The: REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactor trip functional unit shown in Table 3.3.1-2 shall be demonstrated to be within its limit at least once'per 18 months.

Each test shall include at least one channel per trip system 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 system.

An inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur.

In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or the ACTION required by Table 3.3.1-1 for that Trip Function shall be taken.

- The trip system need not be placed in the ' tripped condition if this would cause the Trip Function to occur.

When a trip system can be placed in the tripped condition without causing the Trip Function to occur, place the trip system with the most inoperable channels in the tripped condition; if both systems have the same number of inoperable channels, place either trip system in the tripped condition.

LIMERICK - UNIT 1 3/4 3-1

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TABLE NOTATIONS-l l

. (e).. Manual initiation. isolates the steam supply line outboard isolation valve and only following manual or automatic initiation 'of the system.

(f) In the event of a loss of ventilation the temperature - high setpoint may l.

be raised by 50*F for a period not to exceed 30 minutes to permit restora-tion of. the ventilation flow without a spurious trip. ' During the 30 minute period, an operator, or other qualified member of the technical staff, shall observe the temperature indications continuously, so that, in the event of rapid increases in temperature, the main steam lines shall be manually isolated.

(g) Wide range' accident. monitor per Specification 3.3.7.5.

-l LIMERICK - UNIT 1 3/4 3-17 Amendment No. 28

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TABLE 3.3.2-3 ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION RESPONSE TIME'(Seconds)#

1.

MAIN STEAM LINE ISOLATION a.

Reactor Vessel Water Level 1)

Low, Low - Level 2

< 13(a),,

2)

' Low, Low, Low - Level 1 51.0*

Main Steam Line (b) b.

Radiation - Higb 5 1.0*/1 13(a),,

c.

Main Steam.Line Pressure - Low 1 1.0*/5 13(a),,

d.

Main Steam Line Flow - High 5 0.5*/5 13(a),a e.

Condenser Vacuum - Low N.A.

f.

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g.

Turbine Enclosure - Main Steam Line Tunnel Temperature - High N.A, h.

Manual Initiation N. A.

2.

RHR SYSTEM SHUTDOWN COOLING MODE ISOLATION a.

Reactor Vessei Water Level

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Reactor Vessel (RHR Cut-In Permissive) Pressure - High N.A.

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1 3.

REACTOR WATER CLEANUP SYSTEM ISOLATION a.

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c.'

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d.

S'LCS Initiation N. A.

e.

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Manual Initiation N.A.

LIMERICK - UNIT 1 3/4 3-23 Amendment No. 28

TABLE 3.3.2-3 (Continued)

ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME i

TRIP FUNCTION RESPONSETIME(Secondsl#

4.

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c.

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d.

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e.

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f.

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g.

Manual Initiation N.A.

b 5.

REACTORCOREISOLATIONCdOLINGSYSTEMISOLATION a.

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RCIC Steam Supply Pressure - Low 1 13(a) c.

RCIC Turbine Exhaust Diaphragm Pressure - High N.A.

d.

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e.

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f.

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g.

Manual Initiation N.A.

LIMERICK - UNIT 1 3/4 3-24

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REACTOR COOLANT SYSTEM

' OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.3.2 Reactor coolant system leakage shall be limited to:

a '.

No PRESSURE BOUNDARY LEAKAGE.

b.

5 gpm UNIDENTIFIED LEAKAGE.

c.

30 gpm total leakage.

d.

25 gpm total leakage averaged over any 24-hour period.

e.

1 gpm leakage at a reactor coolant system pressure of 950 10 psig from any reactor coolant system pressure isolation valve specified in Table 3.4.3.2-1 APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

a.

With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

With any reactor coolant system leakage greater than the limits in b, c, and/or d.,.above,' reduce the leakage rate to within the limits l

within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c.

With any reactor coolant system pressure isolation valve leakage greater

-than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one other closed manual, deactivated automatic, or check

valves, or

-be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

d.

With one or more of the high/ low pressure interface valve leakage pressure monitors shown in Table 3.4.3.2-1 inoperable, restore the inoperable monitor (s) to OPERABLE status within 7 days or verify the pressure to be less than the alarm setpoint at least once per.12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ; restore the inoperable monitor (s) to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

khich have been verified not to exceed the allowable leakage limit at the last refueling outage or after the last time the valve was disturbed, whichever is more'recent.

Amendment No. 28 LIMERICK - UNIT 1 3/4 4-9

L SURVEILLANCE REQUIREMENTS

~

4.4.3.2.1 The reactor coolant system leakage shall be demonstrated to be within each of the above limits by:

a.

Monitoring the primary containment atmospheric gaseous radioactivity at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (not a means of quantifying leakage),

b.

Monitoring the drywell floor drain sump and drywell equipment drain tank flow rate at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , c.

Monitoring the drywell unit coolers condensate flow rate at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , d.

Monitoring the primary containment pressure at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (not a means of quantifying leakage),

e.

Monitoring the reactor vessel head flange leak detection system at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,-and f.

Monitoring the primary containment temperature at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (not a means of quantifying leakage).

4.4.3.2.2 Each reactor coolant system pressure isolation valve specified in Table 3.4.3.2-1 shall be demonstrated OPERABLE by leak testing pursuant to Specification 4.0.5 and verifying the leakage of each valve to be within the i

specified limit:

a.

At least once per 18 _ months, and b.

Prior to returning the valve to service following maintenance, repair or replacement work on the valve which could affect its leakage rate.

'The provisions of Specification 4.0.4 are not applicable for entry into OPERATIONAL CONDITION 3.

1 4.4.3.2.3 The high/ low pressure interface valve leakage pressure monitors shall be demonstrated OPERABLE with alarm setpoints set less than the allowable l

values in Table 3.4.3.2-1 by performance of a:

a.

CHANNEL FUNCTIONAL TEST at least once per 31 days, and b.

CHANNEL CALIBRATION at least once per 18 months.

i e

LI!iERICK - UNIT 1 3/4 4-10 J

CONTAINMENT SYSTEMS 3/4.6.6 PRIMA'RY CONTAINMENT ATMOSPHERE CONTROL PRIMARY CONTAINMENT HYDR 0 GEN RECOMBINER SYSTEMS LIMITING CONDITION FOR OPERATION J

3.6.6.1 Two independent primary containment hydrogen recombiner systems shall be OPERABLE.

APPLICABILITY:

OPERATIONAL CONDITIONS 1 and 2.

ACTION:

With one primary containment hydrogen recombiner system inoperable, restore the inoperable system to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE REQUIREMENTS 4.6.6.1 Each primary containment hydrogen recombiner system shall be demon-strated OPERABLE:

a.

At least once per 6 months by performance of:

1.

A CHANNEL CHECK of all Control Room Recombiner Instrumentation.

2.

A Trickle Heat Circuit check.

3.

A Heater Coil Check.

4.

A verification of valve operation by stroking all the valves to their proper positions.

b.

At least once per 18' months by:

1.

Performing a CHANNEL CALIBRATION of all control room recombiner instrumentation and control circuits.

2.

Verifying the integrity of all heater electrical circuits by perform-ing a resistance to ground test within 30 minutes following the below required functional test.

The resistance to ground for any heater phase shall be greater than or equal to one(1) megohm.

l 3.

Verifying through a visual examination that there is no evidence of abnormal conditions within the recombiner enclosure; i.e., loose wiring or structural connections, deposits of foreign materials, etc.

4.

Verifying during a recombiner system functional test that the minimum heater outlet gas temperature increases to greater than or equal to 1150 F within 120 minutes and maintained for at least one hour.

c.

By measuring the system leakage rate:

1.

As a part of the overall integrated leakage rate test required by Specification 3.6.1.2, or 2.

By measuring the leakage rate of the system outside of the contain-ment isolation valves at P, 44.0 psig, on the schedule required by a

Specification 4.6.1.2, and including the measured leakage as a part of the leakage determined in accordance with Specification 4.6.1.2.

LIMERICK - UNIT 1 3/4 6-57 Amendment No.28

p L

I::

I l:

' CONTAINMENT SYSTEMS DRYWELL HYOROGEN MIXING SYSTEM l'

LIMITING CONDITION FOR OPERATION 3.6.6.2 Four independent drywell unit cooler hydrogen mixing subsystems (1AV212, IBV212,- 1GV212, 1HV212) shall be OPERABLE with each subsystem consist-E ing of one unit cooler fan.

APPLICABILITY: OPERATIONAL CONDITIONS 1 and

ACTION:

With one drywell unit cooler hydro;.. nixing subsystem inoperable, restore the inoperable ' subsystem to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 12 hou SURVEILLANCE REQUIREMENTS 4.6.6.2 Each drywell unit. cooler hydrogen mixing subsystem shall be demonstrated OPERABLE at least once per 92 days by:

a.

Starting the system from the control room, and b.

Verifying that the system operates for at least 15 minutes.

o hl e

LIMERICK - UNIT 1 3/4 6-58

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) e.

Functional Tests During the first refueling shutdown and at least once per 18 months thereafter, a representative sample of snubbers shall be tested using one of the following sample plans for each type of snubber.

The sample plan shall be selected prior to the test period and cannot be changed during the test period.

The NRC Regional Administrator shall be notified in writing of the sample plan selected prior to the test period or the sample plan used in the prior test period shall be implemented:

1)

At least 10% of the total of each type of snubber shall be functionally tested either in place or in a bench test.

For each snubber of a type that does not meet the functional test acceptance criteria of Specification 4.7.4f., an additional 10% of that type of snubber shall be functionally tested until no more failures are found or until all snubbers of that type have been functionally tested; or 2)

A representative sample of each type of snubber shall be functionally tested in accordance with Figure 4.7.4-1.

"C" is the total number of snubbers of a type found not meeting the acceptance requirements of Specification 4.7.4f.

The cumulative number of snubbers of a type tested is denoted by "N'.

At the end of each day's testing, the new values of "N" and "C" (previous day's total plus current day's increments) shall be plotted on Figure 4.7.4-1.

If at any time the point plotted falls on or above the " Reject" line all snubbers of that type shall be functionally tested.

If at any time the point plotted falls on or below the

" Accept" line, testing of snubbers of that type may be terminated.

When the point plotted lies in the " Continue Testing" region, additional snubbers of that type shall be tested until the point falls in the " Accept" region or the " Reject" region, or all the snubbers.of that type have been tested.

Testing equipment failure during functional testing may invalidate that day's testing and allow that day's testing to resume anew at a later time, providing all snubbers tested with the failed equipment during the day of equipment failure are retested; or 3)

An initial representative sample of 55 snubbers of each type shall be functionally tested.

For each snubber type which does not meet the functional test acceptance criteria, another sample of at least one-half the size of the initial sample shall be tested until the total number tested is equal to the initial sample size multiplied by the factor,1 + C/2, xer e '1;

's the number of snubbers found j

which do not meet the fu o'an - wst acceptance criteria.

The J

results from this sampie i Mn shall be plotted using an " Accept" j

line which follows the equation N = 55(1 + C/2).

Each snubber I

point should be plotted as soon ac the snubber is tested.

If the point plotted falls on or below the " Accept" line, testing of that type of snubber may be terminated.

If the point plotted falls l

above the " Accept" line, testing must continue until the point d

falls on or below the " Accept" line or all the snubbers of that j

type have been tested.

1 LIMERICK - UNIT 1 3/4 7-13 Amendment No. 28

~

x f

LPLANT SYSTEMS SURVEILLANCE RE0tlIREMENTS (Continued)

.The representative sample selected for the function test sample

' plans shall be randomly selected from the' snubbers of each type and reviewed before beginning the testing.

The review shall ensure as far as practical that they are representative of the various configu-

. rations, operating environments, range of size, and capacity of snubbers of each, type.

Snubbers placed in'the same locations as

-snubbers which failed the previous functional test shall be retested

'at the time of the next functional test but shall not be included in the sample plan,.and failure of-this functional ~ test;shall not be the-

-sole'cause for increasing the sample size under the sample plan.

If

.during the functional testing, additional sampling is required due to failure of only one' type of snubber, the functional testing results shall be reviewed at the time to determine if additional samples sho_uld be -limited to the type of snubber, which has failed the.

functional testing.-

if.

Functional n st Acceptance Criteria The snubber functional test'shall verify that:

1)

Activation (restraining action) is achieved within the specified range in both tension and compression; 2)

Snubber' bleed, or release rate where required, is present in both tension and compression, within the specified range (hydraulic snubbers only);

13)'

For mechanical snubbers, the force' required to initiate or main-tain motion.of the snubber is within the-specified range in both

. directions of travel;-and 4)

For.. snubbers specifically requirc." not to displace under continuous' load, the ability of the snubber to withstand load without displacement.

Testing methods may be used to measure parameters indirectly or parameters other than those specified if those results can be corre-lated to the specified parameters through established methods.

g.

Functiorsal Test Failure Analysis An engineering evaluation shall be made of each failure to meet the functional test acceptance criteria to determine the cause of the failure.

The results of this evaluation shall be used, if applicable, in selecting snubbers to be tested in an effort to determine the OPERABILITY of other snubbers irrespective of. type which may be subject to the same' failure mode.

For the snubbers found inoperable,*an engineering evaluation shal be performed on the components to which the inoperable snubbers a t attached.

The purpose of this engineering evaluation shall be to determine if the components to which the inoperable snubbers are attached were adversely affected by the inoperability of the snubbers in order to ensure that the component remains capable of meeting the designed service.

I I

LIMERICK - UNIT 1 3/4 7-14 0

t TABLE 6.2.2-1 MINIMUM SHIFT CREW COMPOSITION TWO UNITS WITH A COMMON CONTROL ROOM WITH UNIT (2) IN CONDITION 4 OR 5 OR DEFUELED POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION CMDITION 1, 2, or 3 CONDITION 4 or 5 SS 1*

1*

SR0 1*

1*

l R0 2

1 NLO 2

2**

i STA 1

None j

i WITH UNIT (2) IN CONDITION 1, 2, OR 3

)

POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION CONDITION 1, 2, or 3 CONDITION 4 or 5 SS 1*

1*

SR0 1*

1*

R0 2**

1 NLO 2**

1

)

STA 1*

None I

l TABLE NOTATIONS l

Individual may fill the same position on Unit 2.

- 0ne of the two required individuals may fill the same position on Unit 2.

l SS - Shift Superintendent or Shift Supervisor with a Senior Operator license on Unit 1.

SR0 - Individual with a Senior Operator license on Unit 1.

R0 - individual with an Operator license on Unit 1.

NLO - Non-licensed operator properly qualified to support the unit to which assigned.

STA - Shift Technical Advisor Except for Shift Supervision (SS), the shift crew composition may be one less j

than the minimum requirements of Table 6.2.2-1 for a period of time not to

)

exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew compo-sition to within the minimum requirements of Table 6.2.2-1.

This provision does not permit any shift crew position to be unmanned upon shift change due

. to an oncoming shift crewman being late or absent.

During any absence of Shift Supervision (SS) from the control room while the unit is in OPERATIONAL CONDITION 1, 2, or 3, an individual (other than the Shift Technical Advisor) with a valid Senior Operator license shall be designated to assume the control room command function.

During any absence of Shift Supervision from the control room while the unit is in OPERATIONAL CONDITION 4 or 5, an individual with a valid Senior Operator license or Operator license shall be designated to assume the control room command function.

LIMERICK - UNIT 1 6-5 Amendment No. 28 i

m m-.

)

i

)

ADMINISTRATIVE COWTROLS 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)

FUNCTION 6.2.3.1 The ISEG shall function to erasine unit operating characteristics, j

NRC issuances, industry advisories, Licensee Event Reports, and other sources i

of unit design and operat:ng experience information, including units of simi-lar design, which may indicate areas for improving unit safety.

The ISEG shall make detailed reconnendations for revised procedures, equipment modifications, maintenance activities, operations activities, or other means of improving unit safety.

Such recommendations shall be submitted through the General Manager-Nuclear Quality Assurance to the Senior Vice President-Nuclear.

COMPOSITION 6.2.3.2 The Linierick ISEG shall be composed of at least three, dedicated, full-time.cagineers, including the ISEG Supervisor, located onsite.

Each sna11 have a bachelor's degree in engineering or related science and at least two years professional level experience in his or her field.

The Limerick ISEG Supervisor shall have at least six years of experience in the nuclear field.

The corporate ISEG shall be composed of two dedicated full time engineers each with a Bachelors degree in engineering or related science and at least 2 years professional level experience in his or her field, at least 1 year of which experience shall be in the nuclear field.

The LG5 ISEG reports to the Independent Safety Engineering Manager.

RESPONSIBILITIES 6.2.3.3 The ISEG shall be responsible for maintaining surveillance of unit activities to provide independent verification

that these activities are per-formed correctly and that human errors are reduced as much as practical.

RECOR05 6.2.3.4 Records of activities performed by the ISEG shall be prepared, main-tained, and forwarded each calendar month to the Independent Safety Engineering Manager.

6.2.4 SHIFT TECHNICAL ADV!SOR 6.2.4.1 The Shift Technical Advisor shall provide advisory technical support to Shift Supervision in the areas of thenna) hydraulics, reactor engineering, and plant analysis with regard to safe operation of the unit. The Shift Technical Advisor shall have a bache. lor's degree or equivalent in a scientific or engineer-ing discipline ano shall have received specific training in the response and anal-ysis of the unit for transients and accidents, and in unit design and layout, including the capabilities oi' instrumentation and controls in the control room.

6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifica-tions of ANSI /ANS 3.1-1978 for comparable positions, except for the Senior Health Physicist who shall meet or exceed the qualifications of Regulatory Guide 1.8, Septester 1975.

The licensed Operators and Senior Operators shall also meet or exceed the minieue qualifications of the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees.

"Not responsible for sign-off function.

LIMERICK - UNIT 1 6-6 Amendment No. 10 OCT 3119eg

___

ML20245F862

Text

Attachment:

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