Text

Proposed Tech Specs Section 3/4.8, Plant Sys
	ML17179B076
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Site:	Dresden, Quad Cities
Issue date:	09/10/1993
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ATTACHMENT 3 PROPOSED TECHNICAL SPECIFICATIONS Technical Specification 3/4.8 "PLANT SYSTEMS"

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9309200010 93o9io-11 1

PDR ADOCK 05000237L p

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PLANT SYSTEMS 3.8 - L.IMITING CONDITIONS FOR OPERATION A. Containment Cooling Service Water System At least the following independent containment cooling service water (CCSW) subsystems, with each subsystem comprised of:

1. Two OPERABLE CCSW pumps, and

2.

An OPERABLE flow path capable of taking suction from the ultimate heat sink and transferring the water:

a.

Through one LPCI heat exchanger<al, and separately,

b.

To the associated safety related equipment, shall be OPERABLE:

1.

In OPERATIONAL MODE(s) 1, 2 and 3, two subsystems.

2.

In OPERATIONAL MODE(s) 4, 5 and *,

the subsystem(s) associated with subsystems/loops and components required OPERABLE by Specification 3.8.D.

APPLICABILITY:

OPERATIONAL MODE(s) 1, 2, 3, 4, 5 and

CCSW 3/4.8.A 4.8 - SURVEILLANCE REQUIREMENTS A. Containment Cooling Service Water System Each of the required CCSW subsystems _

shall be demonstrated OPERABLE at least once per 31 days by verifying that each valve, manual, power operated or automatic, in the flow path th'at is not locked, sealed or otherwise secured in position, is in its correct position.

a The LPCI heat exchanger is not required to support operation of the CREFS.

When handling irradiated fuel in the secondary containment, during CORE ALTERATION(s), and operations with a potential for draining the reactor vessel.

DRESDEN - UNITS 2 & 3 3/4.8-1 Amendment No.

PLANT SYSTEMS 3.8 - LIMITING CONDITIONS FOR OPERATION ACTION:

1.

In OPERATIONAL MODE 1, 2 or 3:

a.

With one CCSW pump inoperable, restore the inoperable pump to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 1 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

With one CCSW pump in each subsystem inoperable, restore at least one inoperable pump to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 1 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 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 one CCSW subsystem otherwise inoperable, restore the inoperable subsystem to OPERABLE status with at least one OPERABLE pump within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT SHUTDOWN within the next 1 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 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 both CCSW subsystems otherwise inoperable, restore at least one subsystem to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-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 .

CCSW 3/4.8.A 4.8 - SURVEILLANCE REQUIREMENTS DRESDEN - UNITS 2 & 3 3/4.8-2 Amendment No.

PLANT SYSTEMS 3.8 - LIMITING CONDITIONS FOR OPERATION

2.

In OPERATIONAL MODE 4, 5 or

with the CCSW subsystem which is associated with the safety related equipment required OPERABLE by Specification 3.8.D inoperable, declare the associated safety related equipment inoperable and take the ACTION required by Specification 3.8.D.

CCSW 3/4.8.A 4.8 - SURVEILLANCE REQUIREMENTS When handling irradiated fuel in the secondary containment, during CORE ALTERATION(s), and operations with a potential for draining the reactor vessel.

DRESDEN - UNITS 2 & 3 3/4.8-3 Amendment No.

PLANT SYSTEMS 3.8 - LIMITING CONDITIONS FOR OPERATION B.

Diesel Generator Cooling Water System A diesel generator cooling water (DGCW) subsystem shall be OPERABLE for each required diesel generator with each subsystem comprised of:

1.

One OPERABLE DGCW pump, and

2.

An OPERABLE flow path capable of taking suction from the ultimate heat sink and transferring the water to the associated diesel generator.

APPLICABILITY:

When the diesel generator is required to be OPERABLE.

ACTION:

With one or more DGCW subsystems inoperable, declare the associated diesel generator inoperable and take the ACTION required by Specifications 3.9.A or 3.9.B, as applicable.

DGCW 3/4.8.B 4.8 - SURVEILLANCE REQUIREMENTS B.

Diesel Generator Cooling Water System Each of the required DGCW subsystems shall be demonstrated OPERABLE:

1. At least once per 31 days be verifying that each valve in the flow path that is not locked, sealed or otherwise secured in position, is in its correct position.

2.

At least once per 18 months by verifying that each pump starts automatically upon receipt of a start signal for the associated diesel generator.

DRESDEN - UNITS 2 & 3 3/4.8-4 Amendment No.

PLANT SYSTEMS 3.8 - LIMITING CONDITIONS FOR OPERATION C.

Ultimate Heat Sink The ultimate heat sink shall be OPERABLE with:

1.

A minimum water level at or above elevation 500 ft Mean Sea Level, and

2.

An average water temperature of

s95°F.

APPLICABILITY:

OPERATIONAL MODE(s) 1, 2, 3, 4, 5 and

ACTION:

With the requirements of the above specification not satisfied:

1.

In OPERATIONAL MODE(s) 1, 2 or 3, 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 .

2.

In OPERATIONAL MODE(s) 4 or 5 declare the diesel generator cooling water system inoperable and take the ACTION required by Specification 3.8.B.

3.

In OPERATIONAL MODE *,declare the diesel generator cooling water system inoperable and take the ACTION required by Specification 3.8.B. The provisions of Specification 3.0.C are not applicable.

UHS 3/4.8.C 4.8 - SURVEILLANCE REQUIREMENTS C.

Ultimate Heat Sink The ultimate heat sink shall be determined OPERABLE at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the average water temperature and water level to be within their limits.

When handling irradiated fuel in the secondary containment, during CORE AL TERATION(s), and operations with a potential to drain the reactor vessel.

DRESDEN - UNITS 2 & 3 3/4.8-5 Amendment No.

PLANT SYSTEMS 3.8 - LIMITING CONDITIONS FOR OPERATION D.

Control Room Emergency Filtration System The control room emergency filtration system shall be OPERABLE.

APPLICABILITY:

OPERATIONAL MODE(s) 1, 2, 3, and *.

ACTION:

1.

In OPERATIONAL MODE(s) 1, 2 or 3 with the control room emergency filtration system inoperable, restore the inoperable system to OPERABLE status within 14 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 .

2.

In OPERATIONAL MODE *,with the control room emergency filtration system inoperable, suspend CORE AL TERA Tl 0 N (s), handling of irradiated fuel in the secondary containment and operations with a potential for draining the reactor vessel.

3.

The provisions of Specification 3.0.C are not applicable in OPERATIONAL MODE*.

CREFS 3/4.8.D 4.8 - SURVEILLANCE REQUIREMENTS D.

Control Room Emergency Filtration System The control room emergency filtration system shall be demonstrated OPERABLE:

1. At least once per 1 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months by verifying that the control room air temperature is s95°F.

2.

At least once per 31 days by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months with the heaters operating.

3. At least once per 18 months or. (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system by:

a.

Verifying that the system satisfies the in-place penetration and bypass leakage testing acceptance criteria of <0.05% and uses the test procedure guidance in Regulatory Positions C.5.a, C.5.c and C.5.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 2000 scfm +/- 10%.

b.

Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory When handling irradiated fuel in the secondary containment, during CORE ALTERATION(s), and operations with a potential for draining the reactor vessel.

DRESDEN - UNITS 2 & 3 3/4.8-6 Amendment No.

PLANT SYSTEMS CREFS 3/4.8.D 3.8 - LIMITING CONDITIONS FOR OPERATION 4.8 - SURVEILLANCE REQUIREMENTS DRESDEN - UNITS 2 & 3 3/4.8-7 testing criteria of ASTM-D-3803-89, for a methyl iodide penetration of <0.50%, when tested at 30°C and 70% relative humidity; and

c.

Verifying a system flow rate of 2000 scfm +/- 10% during system operation when tested in accordance with ANSI N510-1980.

4.

After every 1440 hours0.0167 days 0.4 hours 0.00238 weeks 5.4792e-4 months of charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of ASTM-D-3803-89, for a methyl iodide penetration of < 0.50%, when tested at 30°C and 70% relative humidity.

5.

At least once per 18 months by:

a.

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is

< 6 inches water gauge while operating the filter train at a flow rate of 2000 scf m +/- 1 0 %.

b.

Verifying that the filter train starts and isolation dampers close on manual initiation from the control room.

c.

Verifying that during the pressurization mode of operation, control room positive pressure is maintained at ~ 1 /8 inch water gauge relative to adjacent areas during system operation at a flow rate ::::; 2000 scfm.

Amendment No.

PLANT SYSTEMS CREFS 3/4.8.D 3.8 - LIMITING CONDITIONS FOR OPERATION 4.8 - SURVEILLANCE REQUIREMENTS DRESDEN - UNITS 2 & 3 3/4.8-8

d.

Verifying that the heaters dissipate 12 +/- 1.2 kw when tested in accordance with ANSI N510-1980.

This reading shall include the appropriate correction for variations from 480 volts at the bus.

6.

After each complete or partial replacement of an HEPA filter bank by verifying that the HEPA filter bank satisfies the in-place penetration and leakage testing acceptance criteria of

< 0.05% in accordance with ANSI N510-1980 while operating the system at a flow rate of 2000 scfm +/- 10%.

7.

After each complete or partial replacement of an charcoal adsorber bank by verifying that the charcoal adsorber bank satisfies the in-place penetration and leakage testing acceptance criteria of < 0.05% in accordance with ANSI N510-1980 for a halogenated hydrocarbon refrigerant test gas while operating the system at flow rate of 2000 scfm +/- 10%.

Amendment No.

PLANT SYSTEMS 3.8 - LIMITING CONDITIONS FOR OPERATION E.

Flood Protection Flood protection shall be available for all required safe shutdown systems, components and structures.

APPLICABILITY:

At all times.

ACTION:

With the water level, as measured at the Unit 2/3 cribhouse:

1.

Above elevation 506.5 ft Mean Sea Level USGS datum, initiate the applicable flood protection measures.

2.

Above, or predicted to exceed within 3 days, elevation 509.0 ft Mean Sea Level USGS datum, 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 with the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Flood 3/4.8.E 4.8 - SURVEILLANCE REQUIREMENTS E.

Flood Protection The water level at the Unit 2/3 cribhouse shall be determined to be within the limit by:

1.

Measurement at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the water level is below elevation 506.0 ft Mean Sea Level USGS datum, and

2.

Measurement at least once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months when the water level is equal to or above elevation 506.0 ft Mean Sea Level USGS datum.

DRESDEN - UNITS 2 & 3 3/4.8-9 Amendment No.

PLANT SYSTEMS 3.8 - LIMITING CONDITIONS FOR OPERATION F.

Snubbers All required snubbers shall be OPERABLE.

The only snubbers excluded from this requirement are those installed on nonsafety-related systems and then only if their failure or failure of the system on which they are installed would have no adverse impact on any safety-related system.

APPLICABILITY:

OPERATIONAL MODE(s) 1, 2 and 3.

OPERATIONAL MODE(s) 4 and 5 for snubbers located on systems required OPERABLE in OPERATIONAL MODE(s) 4 and 5.

ACTION:

With one or more snubbers inoperable, on any system, within 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months s:

1.

Replace or restore the inoperable snubber(s) to OPERABLE status, and

2.

Perform an engineering evaluation per Specification 4.8.F. 7 on the attached component.

Otherwise, declare the attached system in0perable and follow the appropriate ACTION statement for that system.

Snubbers 3/4.8.F 4.8 - SURVEILLANCE REQUIREMENTS F.

Snubbers Each snubber shall be demonstrated OPERABLE by the performance of the following augmented inservice inspection program in addition to the requirements of Specification 4.0.E.

1.

Inspection Types As used in this sp?cification, "type of snubber" shall mean snubbers of the same design and manufacturer, irrespective of capacity.

2.

Visual Inspections Snubbers are categorized as inaccessible or accessible during reactor operation. Each of these categories (inaccessible and accessible) may be inspected independently according to the schedule determined by Table 4.8.F-1. The visual inspection interval for each type of snubber shall be determined based upon the criteria provided in Table 4.8.F-1 la>.

3.

Visual Inspection Acceptance Criteria Visual inspections shall verify that:

(1) the snubber has no visible indications of damage or impaired OPERABILITY, (2) attachments to the fo1.,mdation or supporting structure are functional, and (3) fasteners for the attachment of the snubber to the component and to the snubber anchorage are functional. Snubbers which appear inoperable as a result of a

The first inspection interval determined using this criteria shall be based upon the previous inspection interval as established by the requirements in effect before amendment (

).

DRESDEN - UNITS 2 & 3 3/4.8-10 Amendment No.

PLANT SYSTEMS Snubbers 3/4.8.F 3.8 - LIMITING CONDITIONS FOR OPERATION 4.8 - SURVEILLANCE REQUIREMENTS DRESDEN - UNITS 2 & 3 3/4.8-11 visual inspections shall be classified as unacceptable. A review and evaluation shall be performed and documented to justify continued operation with an unacceptable snubber. If continued operation cannot be justified, the snubber shall be declared inoperable and the ACTION requirements shall be met.

Snubbers originally classified as unacceptable may be reclassified as acceptable for the purpose of establishing the next visual inspection interval, provided that: (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers irrespective of type that may be generically susceptible; and (2) the affected snubber is functionally tested in the as-tound condition and determined OPERABLE per Specification 4.8.F.6.

4.

Transient Event Inspection An inspection shall be performed of all snubbers attached to sections of systems that have experienced unexpected, potentially damaging transients, as determined from a review of operational data or a visual inspection of the systems, within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for accessible systems and 6 months for inaccessible systems following this determination. In addition to satisfying the visual inspection acceptance criteria, freedom-of-motion of mechanical snubbers shall be verified using at least one of the following: (1) manually induced snubber movement; or (2) evaluation of in-place snubber piston setting; or (3) stroking the mechanical snubber through its full range of travel.

Amendment No.

PLANT SYSTEMS Snubbers 3/4.8.F 3.8 - LIMITING CONDITIONS FOR OPERATION 4.8 - SURVEILLANCE REQUIREMENTS DRESDEN - UNITS 2 & 3 3/4.8-12

5.

Functional Tests At least once per 18 months, 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:

a.

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 4.8.F.6, 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

b.

A representative sample of each type of snubber shall be functionally tested, in accordance with Figure 4.8.F-1. "C" is the total number of snubbers of a type found not meeting the acceptance requirements of Specification 4.8.F.6. 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 4.8.F-1.

Amendment No.

PLANT SYSTEMS Snubbers 3/4.8.F 3.8 - LIMITING CONDITIONS FOR OPERATION 4.8 - SURVEILLANCE REQUIREMENTS DRESDEN - UNITS 2 & 3 3/4.8-13 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

c.

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, where "C" is the number of snubbers found which do not meet the functional test acceptance criteria. The results from this sample plan shall be plotted using an "Accept" line which follows the equation N = 55(1 + C/2). Each snubber point should be plotted as soon as the snubber is tested. If the point plotted falls on or below the Amendment No.

PLANT SYSTEMS Snubbers 3/4.8.F 3.8 - LIMITING CONDITIONS FOR OPERATION 4.8 - SURVEILLANCE REQUIREMENTS DRESDEN - UNITS 2 & 3 3/4.8-14 "Accept" line, testing of that type of snubber may be terminated. If the point plotted falls above the "Accept" line, testing must continue until the point falls on or below the "Accept" line or all the snubbers of that type have been tested.

The representative sample selected for the functional 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 configurations, operating environments, range of size, and capacity of snubbers of each type.

Snubbers placed in the same location 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 testing, additional sampling is required due to failure of only on type of snubber, the functional testing results shall be*

reviewed at the time to determine if additional samples should be limited to the type of snubber which has failed the functional testing.

6.

Functional Test Acceptance Criteria The snubber functional test shall verify that:

a.

Activation (restraining action) is achieved within the specified range in both tension and compression; Amendment No.

PLANT SYSTEMS Snubbers 3/4.8.F 3.8 - LIMITING CONDITIONS FOR OPERATION 4.8 - SURVEILLANCE REQUIREMENTS DRESDEN - UNITS 2 & 3 3/4.8-15

b.

The force required to initiate or maintain motion of the snubber is within the specified range in both directions of travel; and

c.

For snubbers specifically required 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 correlated to the specified parameters through established methods.

7.

Functional Test Failure Analysis An engineering evaluation shall be made of each failure to meet the functional test acceptance criteria to determine the cause for 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 shall be performed on the components to which the inoperable snubbers are 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.

Amendment No.

PLANT SYSTEMS Snubbers 3/4.8.F 3.8 - LIMITING CONDITIONS FOR OPERATION 4.8 - SURVEILLANCE REQUIREMENTS DRESDEN - UNITS 2 & 3 3/4.8-16 If any snubber selected for functional testing either fails to lock up or fails to move, i.e., frozen-in-place, the cause will be evaluated and, if caused by manufacturer or design deficiency, all snubbers of the same type subject to the same defect shall be functionally tested. This testing requirement shall be independent of the requirements stated in Specification 4.8.F.5 for snubbers not meeting the functional test acceptance criteria.

8.

Functional Testing of Repaired and Replaced Snubbers Snubbers which fail the visual inspection or the functional test acceptance criteria shall be repaired or replaced. Replacement snubbers and snubbers which have repairs which might affect the functional test result shall be tested to meet the functional test criteria before installation in the unit. Mechanical snubbers shall have met the acceptance criteria subsequent to their most recent service, and the freedom-of-motion test must have been performed within 12 months before being installed in the unit.

9.

Snubber Service Life Program The service life of all snubbers shall be monitored to ensure that the service life is not exceeded between surveillance inspections. The maximum expected service life for various seals, springs, and other critical parts shall be extended or shortened based on monitored test results and failure history. Critical parts shall be replaced so that the maximum service life will not be exceeded during a period when Amendment No.

PLANT SYSTEMS Snubbers 3/4.8.F 3.8 - LIMITING CONDITIONS FOR OPERATION 4.8 - SURVEILLANCE REQUIREMENTS DRESDEN - UNITS 2 & 3 3/4.8-17 the snubber is required to be OPERABLE. The parts replacements shall be documented and the documentation shall be retained in accordance with Specification 6.5.B.

Amendment No.

PLANT SYSTEMS Snubbers 3/4.8.F TABLE 4.8.F-1 SNUBBER VISUAL INSPECTION CRITERIA NUMBER OF UNACCEPTABLE SNUBBERS Population<aHbl Column A lcllfl Column B ldllfl Column C lel!fl or Category Extend Interval Regeat Interval Reduce Interval 1

0 0

1 80 0

0 2

100 0

1 4

150 0

3 8

200 2

5 13 300 5

12 25 400 8

18 36 500 12 24 48 750 20 40 78 2::1000 29 56 109 a

The next visual inspection interval for a snubber population or category size shall be determined based upon the previous inspection interval and the number of unacceptable snubbers found during that interval. Snubbers may be categorized, based upon their accessibility during power operation, as accessible or inaccessible. These categories may be examined separately or jointly. However, the decision must be made and documented before any inspection and shall be used as the basis upon which to determine the next inspection i.nterval for that category.

b Interpolation between population or category sizes and the number of unacceptable snubbers is permissible. Use next lower integer for the value of the limit for Columns A, B, or C if that integer includes a fractional value of unacceptable snubbers as determined by interpolation.

c If the number of unacceptable snubbers is equal to or less than the number in Column A, the next inspection interval may be twice the previous interval, but not greater than 48 months.

d If the number of unacceptable snubbers is equal to or less than the number in Column B but greater than the number in Column A, the next inspection interval shall be the same as the previous interval.

e If the number of unacceptable snubbers is equal to or greater than the number in Column C, the next inspection interval shall be two-thirds of the previous interval, but not less than 31 days. However, if the number of unacceptable snubbers is less than the number in Column C but greater than the number in Column B, the next interval shall be reduced proportionally by interpolation, that is, the previous interval shall be reduced by a factor that is one-third of the ratio of the difference between the number of unacceptable snubbers found during the previous interval and the number in Column B to the difference in the numbers in Columns B and C.

f DRESDEN - UNITS 2 & 3 Amendment No.

The provisions of Specification 4.0.B are applicable for all inspection intervals up to and including 48 months.

3/4.8-18

PLANT SYSTEMS Snubbers 3/4.8.F FIGURE 4.8.F-1 SAMPLING PLAN FOR SNUBBER FUNCTIONAL TESTING 10 9

8 7

6 0

5 4

3 2

1 0

~

I REJECT I I

I v~

,,~!..--

~

I c~

_v v-CONTINUE

~

TESTING.

~

...r ~ ~

~

I ACCEPT I

~

I I

v

~

0 10 20 30 40 50 N

60 70 80 90 100 N = Cumulative number of snubbers of a type tested.

C = Total number of snubbers of a type not meeting acceptance requirements.

DRESDEN - UNITS 2 & 3 3/4.8-19 Amendment No.

PLANT SYSTEMS 3.8 - LIMITING CONDITIONS FOR OPERATION G.

Sealed Source Contamination Each sealed source containing radioactive material either in excess of 1 00 µCi of beta and/or gamma emitting material or 5 µCi of alpha emitting material shall be free of

~0.005 µCi of removable contamination.

APPLICABILITY:

At all times.

ACTION:

1. With a sealed source having removable contamination in excess of the above limit, withdraw the sealed source from use and either:

a.

Decontaminate and repair the sealed source, or

b.

Dispose of the sealed source in accordance with Commission Regulations.

2.

With a sealed source leakage test revealing the presence of removable contamination in excess of the above limit, a report shall be prepared and submitted to the Commission on an annual basis.

3.

The provisions of Specification 3.0.C are not applicable.

Sealed Sources 3/4.8.G 4.8 - SURVEILLANCE REQUIREMENTS G.

Sealed Source Contamination

1.

Test Requirements - Each sealed source shall be tested for leakage and/or contamination by:

a.

The licensee, or

b.

Other persons specifically authorized by the Commission or an Agreement State.

The test method shall have a detection sensitivity of at least 0.005 µCi per test sample.

2.

Test Frequencies - Each category of sealed sources, excluding startup sources and fission detectors previously subjected to core flux, shall be tested at the frequency described below.

a.

Sources in use - At least once per 6 months for all sealed sources containing radioactive material:

1)

With a half-life > 30 days, excluding Hydrogen 3, and

2)

In any form other than gas.

b.

Stored sources not in use - Each sealed source shall be tested prior to use or transfer to another licensee unless tested within the previous 6 months. Sealed sources transferred without a certificate indicating the last test date shall be tested prior to being placed into use.

DRESDEN - UNITS 2 & 3 3/4.8-20 Amendment No.

PLANT SYSTEMS Sealed Sources 3/4.8.G 3.8 - LIMITING CONDITIONS FOR OPERATION 4.8 - SURVEILLANCE REQUIREMENTS DRESDEN - UNITS 2 & 3 3/4.8-21

c.

Startup sources and fission detectors - Each sealed startup source and fission detector shall be tested within 31 days prior to being subjected to core flux or installed in the core and following repair or maintenance to the source.

Amendment No.

PLANT SYSTEMS 3.8 - LIMITING CONDITIONS FOR OPERATION H.

Offgas Explosive Mixture The concentration of hydrogen in the offgas holdup system shall be limited to s4% by volume.

APPLICABILITY:

During offgas holdup system operation.

ACTION:

With the concentration of hydrogen in the offgas holdup system exceeding the limit, restore the concentration to within the limit within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . The provisions of Specification 3.0.C are not applicable.

Offgas Explosive Mixture 3/4.8.H 4.8 - SURVEILLANCE REQUIREMENTS H.

Offgas Explosive Mixture The concentration of hydrogen in the offgas holdup system shall be determined to be within the above limits as required by Table 3.2.H-1 of Specification 3.2.H.

DRESDEN - UNITS 2 & 3 3/4.8-22 Amendment No.

PLANT SYSTEMS 3.8 - LIMITING CONDITIONS FOR OPERATION I.

Main Condenser Offgas Activity The release rate of the sum of the activities of the noble gases measured prior to the offgas holdup line shall be limited to s 100 µCi/sec/MWt, after 30 minutes decay.

APPLICABILITY:

OPERATIONAL MODE(s) 1, 2lal and 3la>.

ACTION:

With the release rate of the sum of the activities of the noble gases at the main condenser air ejector effluent (as measured prior to the offgas holdup line)

> 100 µCi/sec/MWt, after 30 minutes decay, restore the release rate to within its limit within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least STARTUP with the main steam isolation valves closed within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

a When the main condenser air ejector is in operation.

Offgas Activity 3/4.8.1 4.8 - SURVEILLANCE REQUIREMENTS I.

Main Condenser Offgas Activity 1 ;

The release rate of noble gases from the main condenser air ejector shall be continuously monitored in accordance with the ODCM.

2.

The release rate of the sum of the activities from noble gases from the main condenser air ejector shall be determined to be within the limits of Specification 3.8.1 at the following frequencies1bl by performing an isotopic analysis of a representative sample of gases taken at the recombiner outlet, or the air ejector outlet, if the recombiner is bypassed:

a.

At least once per 31 days, and

b.

Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months following the determination of an increase, as indicated by the air ejector noble gas monitor, of > 50%, after factoring out increases due to changes in THERMAL POWER level, in the nominal steady state fission gas release from the primary coolant.

b The provisions of Specification 4.0.D are not applicable:

DRESDEN - UNITS 2 & 3 3/4.8-23 Amendment No.

PLANT SYSTEMS 3.8 - LIMITING CONDITIONS FOR OPERATION J.

Liquid Holdup Tanks The quantity of radioactive material contained in each of the following tanks shall be limited to -::f0.7 curies and the total of all the tanks shall not exceed 3.0 curies.

a.

Waste sample tanks,

b.

Floor drain sample tanks,

c.

Waste surge tank, and

d.

Any outside temporary tank used for storage of radioactive liquids.

APPLICABILITY:

At all times.

ACTION:

With the quantity of radioactive material in any of the above identified tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the limit. The provisions of Specification 3.0.C are not applicable.

Liquid Holdup Tanks 3/4.8.J 4.8 - SURVEILLANCE REQUIREMENTS J.

Liquid Holdup Tanks The quantity of radioactive material contained in each of the identified tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank and within 7 days of completion of the addition of radioactive materials to the tank.

DRESDEN - UNITS 2 & 3 3/4.8-24 Amendment No.

PLANT SYSTEMS B 3/4.8 BASES 3/4.8.A Containment Cooling Service Water System The containment cooling service water system, with the ultimate heat sink, provides sufficient cooling capacity for continued operation of the containment cooling system and of other safety-related equipment (e.g., CCSW keep-fill, the control room emergency ventilation system refrigeration units), during normal and accident conditions. The redundant cooling capacity of the system, assuming a single failure, is consistent with the assumptions used in the safety analysis to keep the accident conditions within acceptable limits. Since only one of the four pumps is required to provide the necessary cooling capacity, a thirty day repair period is allowed for one pump out of service.

OPERABILITY of this system is also dependent upon special measures for protection from flooding in the condenser pit area.

3/4.8.B Diesel Generator Cooling Water System The diesel generator cooling water system, with the ultimate heat sink, provides sufficient cooling capacity for continued operation of the diesel generators during normal and accident conditions.

The cooling capacity of the system is consistent with the assumptions used in the safety analysis to keep the accident conditions within acceptable limits. OPERABILITY of this system is also*

dependent upon special measures for protection from flooding in the condenser pit area.

3/4.8.C Ultimate Heat Sink The canals provide an ultimate heat sink with sufficient cooling capacity to either provide normal cooldown of the units, or to mitigate the effects of accident conditions within acceptable limits for one unit while conducting a normal cooldown on the other unit.

3/4.8.D Control Room Emergency Filtration System The control room emergency filtration system maintains habitable conditions for operations personnel during and following all design basis accident conditions. This system, in conjunction with control room design, is based on limiting the radiation exposure to personnel occupying the room to five rem or less whole body; or its equivalent.

The frequency of tests and sample analysis is necessary to show that the HEPA filters and charcoal*

adsorbers can perform as evaluated. The control room emergency filtration system in-place testing procedures are established utilizing applicable sections of ANSI N510-1980 standard. Operation or the system with the heaters OPERABLE for ten hours a month is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters. The charcoal adsorber efficiency test procedures allow for the removal of one representative sample cartridge and testing in accordance with the guidelines of ASTM-D-3803-89.

The sample is at least two inches in diameter and has a length equivalent to the thickness of the bed. If the iodine removal efficiency test results are DRESDEN - UNITS 2 & 3 B 3/4.8-1 Amendment No.

PLANT SYSTEMS B 3/4.8 BASES unacceptable, all adsorbent in the system is replaced. HEPA filter particulate removal efficiency is verified to be at least 99% by in-place testing with a DOP testing medium.

3/4.8.E Flood Protection Flood protection measures are provided to protect the systems and equipment necessary for safe shutdown during high water conditions. The equipment necessary to implement the appropriate measures, as detailed in plant procedures, is required to be available, but not necessarily onsite, to implement the procedures in a timely manner. The selected water levels are based on providing timely protection from the design basis flood of the river.

3/4.8.F Snub be rs Mechanical snubbers are provided to ensure that the structural integrity of the reactor coolant system and all other safety-related systems is maintained during and following a seismic event or other event initiating dynamic loads. Snubbers are classified and grouped by design, manufacturer and accessibility. A list of individual snubbers with information of snubber location, classification or group, and system affected is maintained at the plant. The accessibility of each snubber is determined and documented for each snubber. The determination is based upon the existing radiation levels and the expected time to perform a visual inspection in each snubber location as well as other factors associated with accessibility during plant operation (e.g., temperature, atmosphere, location, etc.), and the recommendations of Regulatory Guides 8.8 and 8.10.

The visual inspection frequency is based upon maintaining a constant level of snubber *protection to the systems. Therefore, the required inspection interval varies with the number of unacceptable snubbers found during the previous inspection, the total population or category size for each snubber type, and the previous inspection interval. A snubber is considered unacceptable if it fails to satisfy the acceptance criteria of the visual inspection. Snubbers may be categorized, based upon their accessibility during power operation, as accessible or inaccessible. These categories may be examined separately or jointly as determined and documented prior to the inspections. The categorization is used as the basis for determining the next inspection interval for that category.

If a review and evaluation can not justify continued operation with an unacceptable snubber, the snubber is declared inoperable and the applicable action taken. To determine the next surveillance interval, the unacceptable snubber may be reclassified as acceptable if it can be demonstrated that the snubber is OPERABLE in its as-found condition by the performance of a functional test. The next visual inspection interval may be twice, the same, or reduced by as much as two-thirds of the previous inspection interval, depending on the number of unacceptable snubbers found in proportion to the size of the population or category for each type of snubber included in the previous inspection. The inspection interval may be as long as 48 months and the provisions of Specification 4.0.B may be applied.

DRESDEN - UNITS 2 & 3 B 3/4.8-2 Amendment No.

PLANT SYSTEMS B 3/4.8 BASES When a snubber is found to be inoperable, an engineering evaluation is performed, in addition to the determination of the snubber mode of failure, in order to determine if any safety-related component or system has been adversely affected by the inoperability of the snubber. The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a significant effect or degradation on the supported component or system.

To provide additional assurance of snubber functional reliability, a representative sample of the installed snubbers will be functionally tested at 18 month intervals. This sample is identified using one of three methods:

1.

Functionally test 10% of a type of snubber with an additional 10% tested for each functional testing failure, or

2.

Functionally test a sample size and determine sample acceptance or rejection using Figure 4.8.F-1, or

3.

Functionally test a representative sample size and determine sample acceptance or rejection using the stated equation.

Figure 4.8.F-1 was developed using "Wald's Sequential Probability Ratio Plan" as described in "Quality Control and Industrial Statistics" by Acheson J~ Duncan.

Permanent or other exemptions from the surveillance program for individual snubbers may be granted by the NRC if a justifiable basis for exemption is presented and, if applicable, snubber life destructive testing was performed to qualify the snubber for the applicable design conditions at either the completion of their fabrication or at a subsequent date. Snubbers so exempted are listed in the list of individual snubbers indicating the extent of the exemptions.

The service life of a snubber is established via manufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubbers, seal replace, spring replaced, in high radiation area, in high temperature area, etc.). The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions. These records provide statistical bases for future consideration of snubber service life.

3/4.8.G Sealed Source Contamination The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium. This limitation will ensure that leakage from byproduct, source, and special nu'clear material sources will not exceed allowable intake values. Sealed sources, including startup sources and fission detectors, are classified into three groups according to their use, with surveillance requirements commensurate with the probability of damage to a source in that group. Those sources which are frequently handled are required to be tested more often than those which are not. Sealed sources which are continuously enclosed DRESDEN - UNITS 2 & 3 B 3/4.8-3 Amendment No.

PLANT SYSTEMS B 3/4.8 BASES within a shielded mechanism, i.e., sealed sources within radiation monitoring or boron measuring devices, are considered to be stored and need not be tested unless they are removed from the shielded mechanism.

3/4.8.H Explosive Gas Mixture This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the offgas holdup system is maintained below the flammability limits of hydrogen and oxygen. Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 1 OCFR Part 50.

3/4.8.1 Main Condenser Offgas Activity Restricting the gross radioactivity rate of noble gases from the main condenser provides reasonable assurance that the total body exposure to an individual at the exclusion area boundary will not exceed a small fraction of the limits of 1 OCFR Part 100 in the event this effluent is inadvertently discharged directly to the environment without treatment. This specification implements the requirements of General Design Criteria 60 and 64 of Appendix A to 1 OCFR Part 50.

3/4.8.J Liquid Holdup Tanks Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 1 OCFR Part 20, Appendix B, Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area. Recirculation of the tank contents for the purpose of reducing the radioactive content is not considered to be an addition of radioactive material to the tank.

DRESDEN - UNITS 2 & 3 B 3/4.8-4 Amendment No.

PLANT SYSTEMS 3.8 - LIMITING CONDITIONS FOR OPERATION A. Residual Heat Removal Service Water.

System At least the following independent residual heat removal service water (RHRS~)

subsystems, with each subsystem comprised of:

1. Two OPERABLE RHRSW pumps, and

2.

An OPERABLE flow path capable of taking suction from the ultimate heat sink and transferring the water:

a.

Through one *RHR heat exchanger, and separately,

b.

To the associated safety related equipment, shall be OPERABLE:

1.

In OPERATIONAL MODE(s) 1, 2 and 3, two subsystems.

2.

In OPERATIONAL MODE(s) 4, 5 and

the subsystem(s) associated with subsystems/loops and components required OPERABLE by Specifications 3.6.0, 3.6.P, 3.8.D, 3.10.K and 3.10.L.

APPLICABILITY:

OPERATIONAL MODE(s) 1, 2, 3, 4, 5 and*.

RHRSW 3/4.8.A 4.8 - SURVEILLANCE REQUIREMENTS A. Residual*Heat Removal Service Water System Each of the required RHRSW subsystems shall be demonstrated OPERABLE at least once per 31 days by verifying that each valve, manual, power operated or automatic, in the flow path that is not locked, sealed or otherwise secured in position, is in its correct position.

When handling irradiated fuel in the secondary containment, during CORE AL TERATION(s), and operations with a potential for draining the reactor vessel.

QUAD CITIES - UNITS 1 & 2 3/4.8-1 Amendment No.

PLANT SYSTEMS 3.8 - LIMITING CONDITIONS FOR OPERATION ACTION:

1.

In OPERATIONAL MODE 1, 2 or 3:

a.

With one RHRSW pump inoperable, restore the inoperable pump to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 1 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

With one RHRSW pump in each subsystem inoperable, restore at least one inoperable pump to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 1 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 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 one RHRSW subsystem otherwise inoperable, restore the inoperable subsystem to OPERABLE status with at least one OPERABLE pump within 7 days or be in at least HOT SHUTDOWN within the next 1 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 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 both RHRSW subsystems otherwise inoperable, restore at least one subsystem to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-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 SHUTDOWNlal within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

RHRSW 3/4.8.A 4.8 - SURVEILLANCE REQUIREMENTS a

Whenever both RHRSW subsystems are inoperable, if unable to attain COLD SHUTDOWN as required by this ACTION, maintain reactor coolant temperature as low as practical by use of alternate heat removal methods.

QUAD CITIES - UNITS 1 & 2 3/4.8-2 Amendment No.

L PLANT SYSTEMS 3.8 - LIMITING CONDITIONS FOR OPERATION

2.

In OPERATIONAL MODE 3 or 4 with the RHRSW subsystem which is associated with an RHR subsystem required OPERABLE by Specification 3.6.0 or 3.6.P inoperable, declare the associated RHR subsystem inoperable and take the ACTION required by Specification 3.6.0 or 3.6.P, as applicable.

3.

In OPERATIONAL MODE 5 with the RHRSW subsystem which is associated with an RHR subsystem required OPERABLE by Specification 3.10.K or 3.1 O.L inoperable, declare the associated RHR subsystem inoperable and take the ACTION required by Specification 3.10.K or 3.1 O.L, as applicable.

4.

In OPERATIONAL MODE

with both unit RHRSW subsystem(s) inoperable, declare the control room emergency filtration system, Train B, inoperable and take the ACTION required by Specification 3.8.D.

RHRSW 3/4.8.A 4.8 - SURVEILLANCE REQUIREMENTS When handling irradiated fuel in the secondary containment, during CORE ALTERATION(s), and operations with a potential for draining the reactor vessel.

QUAD CITIES - UNITS 1 & 2 3/4.8-3 Amendment No.

PLANT SYSTEMS 3.8 - LIMITING CONDITIONS FOR OPERATION B.

Diesel Generator Cooling Water System A diesel generator cooling water (DGCW) subsystem shall be OPERABLE for each required diesel generator with each subsystem comprised of:

1.

One OPERABLE DGCW pump, and

2.

An OPERABLE flow path capable of taking suction from the ultimate heat sink and transferring cooling water to the associated diesel generator.

APPLICABILITY:

When the diesel generator is required to be OPERABLE.

ACTION:

With one or more DGCW subsystems inoperable, declare the associated diesel generator inoperable and take the ACTION required oy Specifications 3.9.A or 3.9.B, as applicable.

DGCW 3/4.8.B 4.8 - SURVEILLANCE REQUIREMENTS B.

Diesel Generator Cooling Water System Each of the required DGCW subsystems shall be demonstrated OPERABLE:

1. At least once per 31 days by verifying that each valve in the flow path that is not locked, sealed or otherwise secured in position, is in its correct positon.

2.

At least once per 18 months by verifying that each pump starts automatically upon receipt of a start signal for the associated diesel generator.

QUAD CITIES - UNITS 1 & 2 3/4.8-4 Amendment No.

PLANT SYSTEMS 3.8 - LIMITING CONDITIONS FOR OPERATION C.

Ultimate Heat Sink The ultimate heat sink shall be OPERABLE with:

1.

A minimum water level at or above elevation 561 ft Mean Sea Level, and

2.

An average water temperature of

595°F.

APPLICABILITY:

OPERATIONAL MODE(s) 1, 2, 3, 4, 5 and *.

ACTION:

With the requirements of the above specification not satisfied:

1.

In OPERATIONAL MODE(s) 1, 2 or 3, 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 .

2.

In OPERATIONAL MODE(s) 4 or 5 declare the RHRSW system and the diesel generator cooling water system inoperable and take the ACTION(s) required by Specifications 3.8.A and 3.8.B.

3.

In OPERATIONAL MODE *,declare the diesel generator cooling water system inoperable and take the ACTION(s) required by Specification 3.8.B. The provisions of Specification 3.0.C are not applicable.

UHS 3/4.8.C 4.8 - SURVEILLANCE REQUIREMENTS C.

Ultimate Heat Sink The ultimate heat sink shall be determined OPERABLE at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the average water temperature and water level to be within their limits.

When handling irradiated fuel in the secondary containment, during CORE ALTERATION(s), and operations with a potential for draining the reactor vessel.

QUAD CITIES - UNITS 1 & 2 3/4.8-5 Amendment No.

PLANT SYSTEMS 3.8 - LIMITING CONDITIONS FOR OPERATION D.

Control Room Emergency Filtration System The control room emergency filtration system shall be OPERABLE.

APPLICABILITY:

OPERATIONAL MODE(s) 1, 2, 3, and

ACTION:

1.

In OPERATIONAL MODE(s) 1, 2 or 3 with the control room emergency filtration system inoperable, restore the inoperable system to OPERABLE status within 14 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 .

2.

In OPERATIONAL MODE *, with the control room emergency filtration system inoperable, suspend CORE ALTERATION(s), handling of irradiated fuel in the secondary containment and operations with a potential for draining the reactor vessel.

3.

The provisions of Specification 3.0.C are not applicable in OPERATIONAL MODE*.

CREFS 3/4.8.D 4.8 - SURVEILLANCE REQUIREMENTS D.

Control Room Emergency Filtration System The control room emergency filtration system shall be d.~monstrated OPERABLE:

1. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that the control room air temperature is

s;95°F.

2.

At least once per 31 days by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months with the heaters operating.

3.

At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire

or chemical release in any ventilation zone communicating with the system by:

a.

Verifying that the system satisfies the in-place penetration and bypass leakage testing acceptance criteria of < 0.05% and uses the test procedure guidance in Regulatory Positions C.5.a, C.5.c and C.5.d of Regulatory Guide 1 ~52, Revision 2, March 1978, and the system flow rate is 2000 scfm +/- 1 0 %.

b.

Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory.

When handling irradiated fuel in the secondary containment, during CORE ALTERATION(s), and operations with a potential for draining the reactor vessel.

QUAD CITIES - UNITS 1 & 2 3/4.8-6 Amendment No.

PLANT SYSTEMS CREFS 3/4.8.D 3.8 - LIMITING CONDITIONS FOR OPERATION 4.8 - SURVEILLANCE REQUIREMENTS QUAD CITIES - UNITS 1 & 2 3/4.8-7 testing criteria of ASTM-D-3803-89, for a methyl iodide penetration of <0.50%, when tested at 30°C and 70% relative humidity; and c... Verifying a system flow rate of 2000 scfm +/- 10% during system operation when tested in accordance with ANSI N510-1980.

4. After every 1440 hours0.0167 days 0.4 hours 0.00238 weeks 5.4792e-4 months of charcoal adsorber operation by verifying within 31 days after removal that a laboratory _

analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of ASTM-D-3803-89, for a methyl iodide penetration of <0.50%, when tested at 30°C and 70% relative humidity.

5.

At least once per 18 months by:

a.

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is

< 6 inches water gauge while operating the filter train at a flow rate of 2000 scfm +/- 1 0 %.

b.. Verifying that the isolation dampers close on each of the following signals:

1)

Manual initiation from the control room, and

2)

Simulated automatic isolation signal.

c.

Verifying that during the pressurization mode of operation, control room positive pressure is maintained at ~ 1 /8 inch water gauge relative to adjacent areas during system operation at a flow rate =::;; 2000 scfm.

Amendment No.

PLANT SYSTEMS CREFS 3/4.8.D 3.8 - LIMITING CONDITIONS FOR OPERATION 4.8 - SURVEILLANCE REQUIREMENTS QUAD CITIES - UNITS 1 & 2 3/4.8-8

d.

Verifying that the heaters dissipate 12 +/- 1.2 kw when tested in accordance with ANSI N510-1980.

This reading shall include the appropriate correction for variations from 480 volts at the bus.

6.

After each complete or partial replacement of an HEPA filter bank by verifying that the HEPA filter bank satisfies the in-place penetration and leakage testing acceptance criteria of

<0.05% in accordance with ANSI N510-1980 while operating the system at a flow rate of 2000 scfm +/- 10%.

7.

After each complete or partial replacement of an charcoal adsorber bank by verifying that the charcoal adsorber bank satisfies the in-place penetration and leakage testing acceptance criteria of < 0.05% in accordance with ANSI N510-1980 for a halogenated hydrocarbon refrigerant test gas while operating the system at flow rate of 2000 scfm +/- 10%.

Amendment No.

PLANT SYSTEMS 3.8 - LIMITING CONDITIONS FOR OPERATION E.

Flood Protection Flood protection shall be available for all required safe shutdown systems, components and structures.

APPLICABILITY:

At all times.

ACTION:

With the water level, as measured at the plant intake bay:

1.

Above elevation 586 ft Mean Sea Level USGS datum, initiate the applicable flood protection measures.

2.

Above, or predicted to exceed within 3 days, elevation 594 ft Mean Sea Level USGS datum, be in at least HOT SHUTDOWN within the next 1 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Flood 3/4.8.E 4.8 - SURVEILLANCE REQUIREMENTS E.

Flood Protection The water level at the plant intake bay shall be determined to be within the limit by:

1.

Measurement at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the water level is below elevation 585.5 ft Mean Sea Level USGS datum, and

2.

Measurement. at least once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months when the water level is equal to or above elevation 585.5 ft Mean Sea Level USGS datum.

QUAD CITIES - UNITS 1 & 2 3/4.8-9 Amendment No.

PLANT SYSTEMS 3.8 - LIMITING CONDITIONS FOR OPERATION F.

Snubbers All required snubbers shall be OPERABLE.

The only snubbers excluded from this requirement are those installed on nonsafety-related systems and then only if their failure or failure of the system on which they are installed would have no adverse impact on any safety-related system.

APPLICABILITY:

OPERATIONAL MODE(s) 1, 2 and 3.

OPERATIONAL MODE(s) 4 and 5 for snubbers located on systems required OPERABLE in OPERATIONAL MODE(s) 4 and 5.

ACTION:

With one or more snubbers inoperable, on any system, within 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months s:

1.

Replace or restore the inoperable snubber(s) to OPERABLE status, and

2.

Perform an engineering evaluation per Specification 4.8.F. 7 on the attached component.

Otherwise, declare the attached system inoperable and follow the cippropriate ACTION statement for that system.

Snubbers 3/4.8.F 4.8 - SURVEILLANCE REQUIREMENTS F.

Snubbers Each snubber shall be demonstrated OPERABLE by the performance of the following augmented inservice inspection program in addition to the requirements of Specification 4.0.E.

1.

Inspection Types As used in this specification, "type of snubber" shall mean snubbers of the same design and manufacturer, irrespective of capacity.

2.

Visual Inspections Snubbers are categorized as inaccessible or accessible during reactor operation. Each of these categories (inaccessible and accessible) may be inspected independently according to the schedule determined by Table 4.8.F-1. The visual inspection interval for each type of snubber shall be determined based upon the criteria provided in Table 4.8.F-1 !al.

3.

Visual Inspection Acceptance Criteria Visual inspections shall verify that:

( 1) the snubber has no visible indications of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are functional, and (3) fasteners for the attachment of the snubber to the component and to the snubber anchorage are functional. Snubbers which appear inoperable as a result of a

The first inspection interval determined using this criteria shall be based upon the previous inspection interval as established by the requirements in effect before amendment (

).

QUAD CITIES - UNITS 1 & 2 3/4.8-10 Amendment No.

PLANT SYSTEMS Snubbers 3/4.8.F 3.8 - LIMITING CONDITIONS FOR OPERATION 4.8 - SURVEILLANCE REQUIREMENTS QUAD CITIES - UNITS 1 & 2 3/4.8-11 visual inspections shall be classified as unacceptable. A review and evaluation shall be performed and documented to justify continued operation with an unacceptable snubber. If continued operation cannot be justified, the snubber shall be declared inoperable and the ACTION requirements shall be met.

Snubbers originally classified as unacceptable may be reclassified as acceptable for the purpose of establishing the next visual inspection interval, provided that: (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers irrespective of type that may be generically susceptible; and (2) the affected snubber is functionally tested in the as-tound condition and determined OPERABLE per Specification 4.8.F.6.

4.

Transient Event Inspection An inspection shall be performed of all snubbers attached to sections of systems that have experienced unexpected, potentially damaging transients, as determined from a review of operational data or a visual inspection of the systems, within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for accessible systems and 6 months for. inaccessible systems following this determination. In addition to satisfying the visual inspection acceptance criteria, freedom-of-motion of mechanical snubbers shall be verified using at least one of the following: (1) manually induced snubber movement; or (2) evaluation of in-place snubber piston setting; or (3) stroking the mechanical snubber through its full range of travel.

Amendment No.

PLANT SYSTEMS Snubbers 3/4.8.F 3.8 - LIMITING CONDITIONS FOR OPERATION 4.8 - SURVEILLANCE REQUIREMENTS QUAD CITIES - UNITS 1 & 2 3/4.8-12

5.

Functional Tests At least once per 1 8 months, 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:

a.

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 4.8.F.6, 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

b.

A representative sample of each type of snubber shall be functionally tested,* in accordance with Figure 4.8.F-1. "C" is the total number of snubbers of a type found not meeting the acceptance requirements of Specification 4.8.F.6. 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 4.8.F-1.

Amendment No.

PLANT SYSTEMS Snubbers 3/4.8.F 3.8 - LIMITING CONDITIONS FOR OPERATION 4.8 - SURVEILLANCE REQUIREMENTS QUAD CITIES - UNITS 1 & 2 3/4.8-13 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 Tes~ing" 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

c.

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, where "C" is the number of snubbers found which do not meet the functional test acceptance criteria. The results from this sample plan shall be plotted using an "Accept" line which follows the equation N = 55(1 + C/2). Each snubber point should be plotted as soon as the snubber is tested. If the point plotted falls on or below the Amendment No.

~------------

PLANT SYSTEMS Snubbers 3/4.8.F 3.8 - LIMITING CONDITIONS FOR OPERATION 4.8 - SURVEILLANCE REQUIREMENTS QUAD CITIES - UNITS 1 & 2 3/4.8-14 "Accept" line, testing of that type of snubber may be terminated. If the point plotted falls above the "Accept" line, testing must continue until the point falls on or below the "Accept". line or all the snubbers of that type have been tested.

The representative sample selected for the functional 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 configurations, operating environments, range of size, and capacity of snubbers of each type.

Snubbers placed in the same location 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 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 should be limited to the type of snubber which has failed the functional testing.

6.

Functional Test Acceptance Criteria The snubber functional test shall verify that:

a.

Activation (restraining action) is achieved within the specified range in both tension and compression; Amendment No.

PLANT SYSTEMS Snubbers 3/4.8.F 3.8 - LIMITING CONDITIONS FOR OPERATION 4.8 - SURVEILLANCE REQUIREMENTS QUAD CITIES - UNITS 1 & 2 3/4.8-15

b.

The force required to initiate or maintain motion of the snubber is within the specified range in both directions of travel; and

c.

For snubbers specifically required 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 correlated to the specified parameters through established methods.

7.

Functional Test Failure Analysis An engineering evaluation shall be made of each failure to meet the functional test acceptance criteria to determine the cause for 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 shall be performed on the components to which the inoperable snubbers are 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.

Amendment No.

PLANT SYSTEMS Snubbers 3/4.8.F 3.8 - LIMITING CONDITIONS FOR OPERATION 4.8 - SURVEILLANCE REQUIREMENTS QUAD CITIES - UNITS 1 & 2 3/4.8-16 If any snubber selected for functional testing either fails to lock up or fails to move, i.e., frozen-in-place, the cause**

will be evaluated and, if caused by manufacturer or design deficiency, all snubbers of the same type subject to the same defect shall be functionally tested. This testing requirement shall be independent of the requirements stated in Specification 4.8.F.5 for snubbers not meeting the functional test acceptance criteria.

8.

Functional Testing of Repaired and Replaced Snubbers Snubbers which fail the visual inspection or the functional test acceptance criteria shall be repaired or replaced. Replacement snubbers and snubbers which have repairs which might affect the functional test result shall be tested to meet the functional test criteria before installation in the unit. Mechanical snubbers shall have met the acceptance criteria subsequent to their most recent service, and the freedom-of-motion test must have been performed within 12 months before being installed in the unit.

9.

Snubber Service Life Program The service life of all snubbers shall be monitored to ensure that the service life is not exceeded between surveillance

. inspections. The maximum expected service life for various seals, springs, and other critical parts shall be extended or shortened based on monitored test results and failure history. Critical parts shall be replaced so that the maximum service life will not be exceeded during a period when Amendment No.

PLANT SYSTEMS Snubbers 3/4.8.F 3.8 - LIMITING CONDITIONS FOR OPERATION 4.8 - SURVEILLANCE REQUIREMENTS QUAD CITIES - UNITS 1 & 2 3/4.8-17 the snubber is required to be OPERABLE. The parts replacements shall be documented and the documentation shall be retained in accordance with Specification 6.5.B.

Amendment No.

PLANT SYSTEMS Snubbers 3/4.8.F TABLE 4.8.F-1 SNUBBER VISUAL INSPECTION CRITERIA NUMBER OF UNACCEPTABLE" SNUBBERS Population<aHbl Column A (c)(fl Column 8 ldl!fl Column C <eHfl or Category Extend Interval ReQeat Interval Reduce Interval 1

0 0

1 80 0

0 2

100 0

1 4

150 0

3 8

200 2

5 13 300 5

12 25 400 8

18 36 500 12 24 48 750 20 40 78

1000 29 56 109 a

The next visual inspection interval for a snubber population or category size shall be determined based upon the previous inspection interval and the number of unacceptable snubbers found during that interval. Snubbers may be categorized, based upon their accessibility during power operation, as accessible or inaccessible. These categories may be examined separately or jointly. However, the decision must be made and documented before any inspection and shall be used as the basis upon which to determine the next inspection interval for that category.

b Interpolation between population or category sizes and the number of unacceptable snubbers is permissible. Use next lower integer for the value of the limit for Columns A, B, or C if that integer includes a fractional value of unacceptable snubbers as determined by interpolation.

c If the number of unacceptable snubbers is equal to or less than the number in Column A, the next inspection interval may be twice the previous interval, but not greater than 48 months.

d If the number of unacceptable snubbers is equal to or less than the.number in Column B but greater than the number in Column A, the next inspection interval shall be the same as the previous interval.

e If the number of unacceptable snubbers is equal to or greater than the number in Column C, the next inspection interval shall be two-thirds of the previous interval, but not less than 31 days. However, if the number of unacceptable snubbers is less than the number in Column C but greater than the number in Column B, the next interval shall be reduced proportionally by interpolation, that is, the previous interval shall be reduced by a factor that is one-third of the ratio of the difference between the number of unacceptable snubbers found during the previous interval and the number in Column B to the difference in the numbers in Columns B and C.

The provisions of Specification 4.0.B are applicable for all inspection intervals up to and including 48 months.

QUAD CITIES - UNITS 1 & 2 3/4.8-18 Amendment No.

PLANT SYSTEMS Snubbers 3/4.8.F FIGURE 4.8.F-1 SAMPLING PLAN FOR SNUBBER FUNCTIONAL TESTING 10 9

8 1

~

~ /'

I REJECT I I

I

/

,,.~Y

~

V" c~.

/

~

CONTINUE

~

TESTlNG

/'

~

...r 1~

v

~

I ACCEPT I

~

I I

/

~

7 6

0 5

4 3

2 0

0 10 20 30 40 50 N

60 70 80 90 100 N = Cumulative number of snubbers of a type tested.

C = Total number of snubbers of a type not meeting acceptance requirements.

QUAD CITIES - UNITS 1 & 2 3/4.8-19 Amendment No.

PLANT SYSTEMS 3.8 - LIMITING CONDITIONS FOR OPERATION G.

Sealed Source Contamination Each sealed source containing radioactive material either in excess of 100 µCi of beta and/or gamma emitting material or 5 µCi of alpha emitting material shall be free of

~0.005 µCi of removable contamination.

APPLICABILITY:

At all times.

ACTION:

1.

With a sealed source having removable contamination in excess of the above limit, withdraw the sealed source from use and either:

a.

Decontaminate and repair the sealed source, or

b.

Dispose of the sealed source in accordance with Commission Regulations.

2. With a sealed source leakage test revealing the presence of removable contamination in excess of the above limit, a report shall be prepared and submitted to the Commission on an annual basis.

3.

The provisions of Specification 3.0.C are not applicable.

Sealed Source 3/4.8.G 4.8 - SURVEILLANCE REQUIREMENTS G.

Sealed Source Contamination

1. Test Requirements - Each sealed source shall be tested for leakage and/or contamination by:

a.

The licensee, or

b.

Other persons specifically authorized by the Commission or an Agreement State.

The test method shall have a detection sensitivity of at least 0.005 µCi per test sample.

2.

Test Frequencies - Each category of sealed sources, excluding startup sources and fission detectors previously subjected to core flux, shall be tested at the frequency described below.

a.

Sources in use - At least once per 6 months for all sealed sources containing radioactive material:

1)

With a half-life > 30 days, excluding Hydrogen 3, and

2)

In any form other than gas.

b.

Stored sources not in use - Each sealed source shall be tested prior to use or transfer to another licensee unless tested within the previous 6 months. Sealed sources transferred without a certificate indicating the last test date shall be tested prior to being placed into use.

QUAD CITIES - UNITS 1 & 2 3/4.8-20 Amendment No.

PLANT SYSTEMS Sealed Source 3/4.8.G 3.8 - LIMITING CONDITIONS FOR OPERATION 4.8 - SURVEILLANCE REQUIREMENTS QUAD CITIES - UNITS 1 & 2 3/4.8-21

c.

Startup sources and fission detectors - Each sealed startup source and fission detector shall be tested within 31 days prior to being subjected to core flux or installed in the core and following repair or maintenance to the source.

Amendment No.

PLANT SYSTEMS 3.8 - LIMITING CONDITIONS FOR OPERATION H.

Offgas Explosive Mixture The concentration of hydrogen in the offgas holdup system shall be limited to :::;;4% by volume.

APPLICABILITY:

During offgas holdup system operation.

ACTION:

With the concentration of hydrogen in the offgas holdup system exceeding the limit, restore the concentration to within the limit within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . The provisions of Specification 3.0.C are not applicable.

Explosive Gas Mixture 3/4.8.H 4.8 - SURVEIL.LANCE REQUIREMENTS H.

Explosive Gas Mixture The concentration of hydrogen in the offgas holdup system shall be determined to be within the above limits as required by Table 3.2.H-1 of Specification 3.2.H.

QUAD CITIES - UNITS 1 & 2 3/4.8-22 Amendment No.

PLANT SYSTEMS 3.8 - LIMITING CONDITIONS FOR OPERATION I.

Main Condenser Offgas Activity The release rate of the sum of the activities of the noble gases measured prior to the offgas holdup line shall be limited to

~ 1 00 µCi/sec/MWt, after 30 minutes decay.

APPLICABILITY:

OPERATIONAL MODE(s) 1, 2lal and 31a1.

ACTION:

With the release rate of the sum of the activities of the noble gases in the main condenser air ejector effluent (as measured prior to the offgas holdup line)

> 100 µCi/sec/MWt, after 30 minutes decay, restore the release rate to within its limit within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least STARTUP with the main steam isolation valves closed within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

a When the main condenser air ejector is in operation.

Offgas Activity 3/4.8.1 4.8 - SURVEILLANCE REQUIREMENTS I.

Main Condenser Offgas Activity 1. The release rate of noble gases from the main condenser air ejector shall be continuously monitored in accordance with the ODCM.

2.

The release rate of the sum of the activities from noble gases from the main condenser air ejector shall be determined to be within the limits of Specification 3.8.1 at the following frequencies(bl by performing an isotopic analysis of a representative sample of gases taken at the recombiner outlet, or the air ejector outlet, if the recombiner is bypassed:

a.

At least once per 31 days, and

b.

Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months following the determination of an increase, as indicated by the air ejector noble gas monitor, of > 50%, after factoring out increases due to changes in THERMAL POWER level, in the nominal steady state fission gas release from the primary coolant.

b The provisions of Specification 4.0.D are not applicable.

QUAD CITIES - UNITS 1 & 2 3/4.8-23 Amendment No.

PLANT SYSTEMS 3.8 LIMITING CONDITIONS FOR OPERATION J.

Safe Shutdown Makeup Pump The Safe Shutdown Makeup Pump (SSMP) shall be OPERABLE.

APPLICABILITY:

OPERATIONAL MODE(s) 1, 2 and 3 with reactor steam dome pressure greater than 150 psig.

ACTION:

1.

With the SSMP system inoperable, restore the inoperable SSMP system to OPERABLE status within 67 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 .

SSMP 3/4.8.J 4.8 - SURVEILLANCE REQUIREMENTS J.

Safe Shutdown Makeup Pump The SSMP system shall be demonstrated OPERABLE:

1. At least once per 31 days by:

a.

Verifying that each valve, manual, power operated or automatic in the flow path that is not locked, sealed or otherwise secured in position, is in its correct position.

b.

Verifying that the pump flow controller is in the correct position.

2. At least once per 92 days by verifying that the SSMP develops a flow of greater than or equal to 400 gpm in the test flow path with a system head corresponding to reactor vessel operating pressure of greater than 1150 psig.

QUAD CITIES - UNITS 1 & 2 3/4.8-24 Amendment No.

PLANT SYSTEMS B 3/4.8 BASES 3/4.8.A Residual Heat Removal Service Water System The residual heat removal service water system, with the ultimate heat sink, provides sufficient cooling capacity for continued operation of the residual heat removal system and of other safety-related equipment, e.g., RHRSW vault coolers and the control room emergency ventilation system refrigeration units, during normal and accident conditions. The redundant cooling capacity of the system, assuming a single failure, is consistent with the assumptions used in the safety analysis to keep the accident conditions within acceptable limits. Since only one of the four pumps is required to provide the necessary cooling capacity, a thirty day repair period is allowed for one pump out of service. OPERABILITY of this system is also dependent upon special measures for protection from flooding in the condenser pit area.

3/4.8.B Diesel Generator Cooling Water System The diesel generator cooling water system, with the ultimate heat sink, provides sufficient cooling capacity for continued operation of the diesel generators during normal and accident conditions.

The cooling capacity of the system is consistent with the assumptions used in the safety analysis to keep the accident conditions within acceptable limits. OPERABILITY of this system is also dependent upon special me13sures for protection from flooding in the condenser pit area.

3/4.8.C Ultimate Heat Sink The Mississippi River provides an ultimate heat sink with sufficient cooling capacity to either provide normal cooldown of the units, or to mitigate the effects of accident conditions within acceptable limits for one unit while conducting a normal cooldown on the other unit.

3/4.8.D Control Room Emergency Filtration System The control room emergency filtration system maintains habitable conditions for operations personnel during and following all design basis accident conditions. This system, in conjunction with control room design, is based on limiting the radiation exposure to personnel occupying the room to five rem or less whole body, or its equivalent.

The frequency of tests and sample analysis is necessary to show that the HEPA filters and charcoal adsorbers can perform as evaluated. The control room emergency filtration system in-place testing procedures' are established utilizing applicable sections of ANSI N510-1980 standard. Operation of the system with the heaters OPERABLE for ten hours a month is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters. The charcoal adsorber efficiency test procedures allow for the removal of one representative sample cartridge and testing in accordance with the guidelines of ASTM-D-3803-89.

The sample is at least two inches in diameter and has a length equivalent to the thickness of the bed. If the iodine removal efficiency test results are QUAD CITIES - UNITS 1 & 2 B 3/4.8-1 Amendment No. 07 /06/93

PLANT SYSTEMS B 3/4.8 BASES unacceptable, all adsorbent in the system is replaced. HEPA filter particulate removal efficiency is verified to be at least 99% by in-place testing with a DOP testing medium.

3/4.8.E Flood Protection Flood protection measures are provided to protect the systems and equipment necessary for safe shutdown during high water conditions. The equipment necessary to implement the appropriate measures, as detailed in plant procedures, is required to be available, but not necessarily onsite, to implement the procedures in a timely manner. The selected water levels are based on providing timely protection from the design basis flood of the river.

3/4.8.F Snubbers Mechanical snubbers are provided to ensure that the structural integrity of the reactor coolant system and all other safety-related systems is maintained during and following a seismic event or other event initiating dynamic loads. Snubbers are classified and grouped by design, manufacturer and accessibility. A list of individual snubbers with information of snubber location, classification or group, and system affected is maintained at the plant. The accessibility of each snubber is determined and documented for each snubber. The determination is based upon the existing radiation levels and the expected time to perform a visual inspection in each snubber location as well as other factors associated with accessibility during plant operation (e.g., temperature, atmosphere, location, etc.), and the recommendations of Regulatory Guides 8.8 and 8.10.

The visual inspection frequency is based upon maintaining a constant level of snubber protection to the systems. Therefore, the required inspection interval varies with the number of unacceptable snubbers found during the previous inspection, the total population or category size for each snubber type, and the previous inspection interval. A snubber is considered unacceptable if it fails to satisfy the acceptance criteria of the visual inspection. Snubbers may be categorized, based upon their accessibility during power operation, as accessible or inaccessible. These categories may be examined separately or jointly as determined and documented prior to the inspections. The categorization is used as the basis for determining the next inspection interval for that category.

If a review and evaluation can not justify continued operation with an unacceptable snubber, the snubber is declared inoperable and the applicable action taken. To determine the next surveillance interval, the unacceptable snubber may be reclassified as acceptable if it can be demonstrated that the snubber is OPERABLE in its as-found condition by the performance of a functional test. The next visual inspection interval may be twice, the same, or reduced by as much as two-thirds of the previous inspection interval, depending on the number of unacceptable snubbers found in proportion to the size of the population or category for each type of snubber included in the previous inspection. The inspection interval may be as long as 48 months and the provisions of Specification 4.0.B may be applied..

QUAD CITIES - UNITS 1 & 2 B 3/4.8-2 Amendment No. 07 /06/93

PLANT SYSTEMS B 3/4.8 BASES When a snubber is found to be inoperable, an engineering evaluation is performed, in addition to the determination of the snubber mode of failure, in order to determine if any safety-related component or system has been adversely affected by the inoperability of the snubber. The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a significant effect or degradation on the supported component or system.

To provide additional assurance of snubber functional reliability, a representative sample of the installed snubbers will be functionally tested at 18 month intervals. This sample is identified using one of three methods:

1.

Functionally test 10% of a type of snubber with an additional 10% tested for each functional testing failure, or

2.

Functionally test a sample size and determine sample acceptance or rejection using Figure 4.8.F-1, or

3.

Functionally test a representative sample size and determine sample acceptance or rejection using the stated equation.

Figure 4.8.F-1 was developed using "Wald's Sequential Probability Ratio Plan" as described in "Quality Control and Industrial Statistics" by Acheson J. Duncan.

Permanent or other exemptions from the surveillance program for individual snubbers may be granted by the NRC if a justifiable basis for exemption is presented and, if applicable, snubber life destructive testing was performed to qualify the snubber for the applicable design conditions at either the completion of their fabrication or at a subsequent date. Snubbers so exempted are listed in the list of individual snubbers indicating the extent of the exemptions; The service life of a snubber is established via manufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubbers, seal replace, spring replaced, in high radiation area, in high temperature area, etc.). The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions. These records provide statistical bases for future consideration of snubber service life.

3/4.8.G Sealed Source Contamination I

The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium. This limitation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values. Sealed sources, including startup sources and fission detectors, are classified into three groups according to their use, with surveillance requirements commensurate with the probability of damage to a source in that group. Those sources which are frequently handled are required to be tested more often than those which are not. Sealed sources which are continuously enclosed QUAD CITIES - UNITS 1 & 2 B 3/4.8-3 Amendment No. 07 /06/93

PLANT SYSTEMS B 3/4.8 BASES within a shielded mechanism, i.e., sealed sources within radiation monitoring or boron measuring devices, are considered to be stored and need not be tested unless they are removed from the shielded mechanism.

3/4.8.H Explosive Gas Mixture This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the offgas holdup system is maintained below the flammability limits of hydrogen and oxygen. Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 1 OCFR Part 50.

3/4.8.I Main Condenser Offqas Activity Restricting the gross radioactivity rate of noble gases from the main condenser provides reasonable assurance that the total body exposure to an. individual at the exclusion area boundary will not exceed a small fraction of the limits of 1 OCFR Part 100 in the event this effluent is inadvertently discharged directly to the environment without treatment. This specification implements the requirements of General Design Criteria 60 and 64 of Appendix A to 1 OCFR Part 50.

3/4.8.J Safe Shutdown Makeup Pump System (SSMP)

The SSMP system provides a common backup to the Unit 1 and 2 RCIC systems to satisfy the requirements of 10 CFR 50, Appendix R, Section 111.G, "Fire Protection of Safe Shutdown Capability." The system bypasses fire zones which could theoretically disable the RCIC system.

In the event that the reactor vessel becomes isolated, and the feedwater supply* becomes unavailable, makeup can be provided by manually initiating the SSMP system to supply demineralized makeup water from the CCST or as an alternate source, makeup water from the fire header. The flow rate of the SSMP system is approximately equal to the reactor water boil-off rate 1 5 minutes after shutdown.

The SSMP system is required to be OPERABLE when either Unit 1 or Unit 2 is in OPERATIONAL MODE(s) 1, 2 or 3 with reactor steam dome pressure greater than 150 psig. With the SSMP system inoperable, a 67-day allowable out-of-service (AOT) is provided to restore the inoperable system to OPERABLE status before the Unit(s) must be shut down. (

Reference:

Fire Protection Plan Documentation Package (FPPDP), "Fire Protection Reports," Volume 2, Tab 4, Safe Shutdown Analysis.)

The surveillance requirements provide adequate assurance that the SSMP system will be OPERABLE when required. A design flow test can be performed during plant operation using a full flow test return line to the CCST.

QUAD CITIES - UNITS 1 & 2 B 3/4.8-4 Amendment No. 07 /06/93

ATTACHMENT 4 EXISTING TECHNICAL SPECIFICATIONS Technical Specification 3/4.8 "PLANT SYSTEMS"

ATTACHMENT 4 DELETION OF CURRENT TECHNICAL SPECIFICATIONS This technical specification amendment will replace the current section 3.8/4.8, Plant Systems, for the Dresden Unit 2 and Unit 3 Technical Specifications. The specifications are replaced in its entirety with revised pages that combine the Unit 2 and Unit 3 specifications.

Delete the following pages:

I DPR - 19 I DPR - 25 I I DPR - 19 I DPR - 25 I 3/4.8-1 3/4.8-1 3/4.8-24 3/4.8-23 3/4.8-2 3/4.8-2 3/4.8-25 3/4.8-24 3/4.8-3 3/4.8-3 3/4.8-26 3/4.8-25 3/4.8-4 3/4.8-4 3/4.8-27 3/4.8-26 3/4.8-5 3/4.8-5 3/4.8-28 3/4.8-28 3/4.8-6 3/4.8-6 3/4.8-29 3/4.8-29 3/4.8-7 3/4.8-7 3/4.8-30 3/4.8-30 3/4.8-8 3/4.8-8 3/4.8-31 3/4.8-31 3/4.8-9 3/4.8-9 B 3/4.8-32 B 3/4.8-32 3/4.8-10 3/4.8-10 B 3/4.8-33 B 3/4.8-33 3/4.8-11 3/4.8-11 B 3/4.8-34 B 3/4.8-34 3/4.8-12 3/4.8-12 B 3/4.8-35 B 3/4.8-35 3/4.8-13 3/4.8-13 B 3/4.8-36 B 3/4.8-36 3/4.8-14 3/4.8-14 B 3/4.8-37 B 3/4.8-37 3/4.8-15 3/4.8-15 B 3/4.8-38 B 3/4.8-38 3/4.8-16 3/4.8-16 B 3/4.8-39 B 3/4.8-39 3/4.8-17 3/4.8-17 B 3/4.8-40 B 3/4.8-40 3/4.8-18 3/4.8-18 B 3/4.8-41 B 3/4.8-41 3/4.8-19 3/4.8-19 3/4.8-20 3/4.8-20 3/4.8-21 3/4.8-21 3/4.8-22 3/4.8-22 3/.11. R-?::l 3/4.8-?::l

ATTACHMENT 4 DELETION OF CURRENT TECHNICAL SPECIFICATIONS This technical specification amendment will replace the current section 3.8/4.8, Plant Systems, for the Quad Cities Unit 1 and Unit 2 Technical Specifications. The specifications are replaced in its entirety with revised pages that combine the Unit 1 and Unit 2 specifications.

Delete the following pages:

DPR - 29 DPR - 30 I DPR - 29 I DPR - 30 I 3.8/4.8-1 3.8/4.8-1 3.8/4.8-26 3.8/4.8-21 a 3.8/4.8-2 3.8/4.8-2 3.8/4.8-27 3.8/4.8-22 3.8/4.8-3 3.8/4.8-3 3.8/4.8-28 3.8/4.8-23 3.8/4.8-4 3.8/4.8-4 3.8/4.8-29 3.8/4.8-24 3.8/4.8-5 3.8/4.8-5 3.8/4.8-30 3.8/4.8-25 3.8/4.8-6 3.8/4.8-6 3.8/4.8-31 3.8/4.8-26 3.8/4.8-7 3.8/4.8-6a 3.8/4.8-32 3.8/4.8-27 3.8/4.8-8 3.8/4.8-7 3.8/4.8-33 3.8/4.8-28 3.8/4.8-9 3.8/4.8-7a 3.8/4.8-34 3.8/4.8-29 3.8/4.8-10 3.8/4.8-8 3.8/4.8-35 3.8/4.8-29a 3.8/4.8-11 3.8/4.8-9 3.8/4.8-36 3.8/4.8-30 3.8/4.8-12 3.8/4.8-10 3.8/4.8-37 Figure 4.8-1 3.8/4.8-13 3.8/4.8-11 3.8/4.8-38 3.8/4.8-14 3.8/4.8-12 Figure 4.8-1 3.8/4.8-15 3.8/4.8-13 3.8/4.8-16 3.8/4.8-14 3.8/4.8-17 3.8/4.8-14a 3.8/4.8-18 3.8/4.8-14b 3.8/4.8-19 3.8/4.8-15 3.8/4.8-20 3.8/4.8-16 3.8/4.8-21 3.8/4.8-17 3.8/4.8-22 3.8/4.8-18 3.8/4.8-23 3.8/4.8-19 3.8/4.8-24 3.8/4.8-20

~ 8/4_8-'>I':

~RIA Sl-?1

ATTACHMENT 5 DRESDEN 2/3 DIFFERENCES Technical Specification 3/4.8 "PLANT SYSTEMS"

ATTACHMENT 5 COMPARISON OF DRESDEN UNIT 2 AND UNIT 3 TECHNICAL SPECIFICATIONS FOR THE IDENTIFICATION OF TECHNICAL DIFFERENCES SECTION 3.8/4.8 "Plant Systems" Commonwealth Edison has conducted a comparison review of the Dresden Unit 2 and Unit 3 Technical Specifications to identify any technical differences in support of combining the Technical Specifications into one document. The intent of the review was not to identify any differences in presentation style (e.g. table formats, use of capital letters, etc.),

punctuation or spelling errors, but rather to identify areas which the Technical Specifications are technically or administratively different.

The review of Section 3.8/4.8 "Plant Systems" did not reveal any technical differences.

ATTACHMENTS QUAD CITIES 1/2 DIFFERENCES

Technical Specification 3/4.8 "PLANT SYSTEMS"

ATTACHMENT 5 COMPARISON OF QUAD CITIES UNIT 1 AND UNIT 2 TECHNICAL SPECIFICATIONS FOR THE IDENTIFICATION OF TECHNICAL DIFFERENCES SECTION 3.8/4.8 "Plant Systems" Commonwealth Edison has conducted a comparison review of the Quad Cities Unit 1 and Unit 2 Technical Specifications to identify any technical differences in support of combining the Technical Specifications into one document. The intent of the review was not to identify any differences in presentation style (e.g. table formats, use of capital letters, etc.), punctuation or spelling errors, but rather to identify areas which. the Technical Specifications are technically or administratively different.

The review of Section 3.8/4.8 "Plant Systems" did not reveal any technical differences.

ATTACHMENT 6 SIGNIFICANT HAZARDS CONSIDERATIONS AND ENVIRONMENTAL ASSESSMENT EVALUATION Technical Specification 3/4.8 "PLANT SYSTEMS"

ATTACHMENT 6 EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATION Commonwealth Edison has evaluated this proposed amendment and determined that it involves no significant hazards consideration. According to 10 CFR 50.92(c), a proposed amendment to an operating license involves no significant hazards consideration if operation of the facility, in accordance with the proposed amendment, would not:

1)

Involve a significant increase in the probability or consequences of an accident previously evaluated; or

2)

Create the possibility of a new or *different kind of accident from any accident previously evaluated; or

3)

Involve a significant reduction in a margin of safety.

The proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated because:

In general, the proposed changes represent the conversion of current requirement to a more generic format, or the addition of requirements which are based on the current safety analysis. Implementation of these changes will provide increased reliability of equipment assumed to operate in the current safety analysis, or provide continued assurance that specified parameters remain within their acceptance limits, and as such, will not significantly increase the probability or consequences of a previously evaluated accident.

Some of the proposed changes represent minor curtailments of the current requirements which are based on generic guidance or previously approved provisions for other stations. These proposed changes are consistent with the current safety analyses and have been previously determined to represent sufficient requirements for the assurance and reliability of equipment assumed to operate in the safety analysis, or provide continued assurance that specified parameters remain within their acceptance limits. As such, these changes will not significantly increase the probability or consequences of a previously accident.

The associated systems that make up the Plant Systems are not assumed in any safety analysis to initiate any accident sequence for both Dresden and Quad Cities Stations; therefore, the probability of any accident previously evaluated is not increased by the proposed changes. In addition, the proposed surveillance requirements for the proposed amendments to these systems are more prescriptive than the current requirements specified within the Technical Specifications. The additional surveillance requirements improve the reliability and availability of all affected systems and therefore, reduce the consequences of any accident previously evaluated as the probability of the systems outlined within Section 3/4.8 of the proposed Technical Specifications, performing its intended function is increased by the additional surveillances.

ATTACHMENT 6 Create the possibility of a new or different kind of accident from any previously evaluated because:

In general, the proposed changes represent the conversion of current requirements to a more generic format, or the addition of requirements which are based on the current safety analysis. Others represent minor curtailments of the current requirements which are based on generic guidance or previously approved provisions for other stations. These changes do not involve revisions to the design of the station. Some of the changes may involve revision in the operation of the station; however, these provide additional restrictions which are in accordance with the current safety analysis, or are to provide for additional testing or.

surveillances which will not introduce new failure mechanisms beyond those already considered in the current safety analyses.

The proposed changes for Dresden and Quad Cities Station's Technical Specification Section 3/4.8 are based on STS guidelines or later operating BWR plants' NRC accepted changes. These proposed changes have been reviewed for acceptability at the Dresden and Quad Cities Nuclear Power Stations considering similarity of system or component design versus the STS or later operating BWRs.

No new modes of operation are introduced by the proposed changes, considering the acceptable operational modes in present specifications, the STS, or later operating BWRs. Surveillance requirements are changed to reflect improvements in technique, frequency of performance or operating experience at later plants.

Proposed changes to action statements in many places add requirements that are not in the present technical specifications or adopt requirements that have been used successfully at other operating BWRs with designs similar to Dresden and Quad Cities. The proposed changes maintain at least the present level of operability. Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any previously evaluated.

The associated systems that make up the Plant Systems are not assumed in any safety analysis to initiate any accident sequence for both Dresden and Quad Cities Stations. In addition, the proposed surveillance requirements for affected systems associated with the Primary System Boundary are more prescriptive than the current requirements specified within the Technical Specifications; therefore, the proposed changes do not create the possibility of a new or different kind of accident from any previously evaluated.

Involve a significant reduction in the margin of safety because:

In general, the proposed changes represent the conversion of curre,nt requirements to a more generic format, or the addition of requirements which are based on the current safety analysis. Others represent minor curtailments of the current requirements which are based on generic guidance or previously approved provisions for other stations. Some of the later individual items may introduce minor reductions in the margin of safety when compared to the current requirements. However, other individual changes are the adoption of new

ATTACHMENT 6 requirements which will provide significant enhancement of the reliability of the equipment assumed to operate in the safety analysis, or provide enhanced assurance that specified parameters remain with their acceptance limits. These enhancements compensate for the individual minor reductions, such that taken together, the proposed changes will not significantly reduce the margin of safety.

The proposed changes to Technical Specification Section 3/4.8 implement present requirements, or the intent of present requirements in accordance with the guidelines set forth in the STS. The proposed changes are intended to improve readability, usability, and the understanding of technical specification requirements while maintaining acceptable levels of safe operation. The proposed changes have been evaluated and found to be acceptable for use at Dresden and Quad Cities based on system design, safety analysis requirements and operational performance.

Since the proposed changes are based on NRC accepted provisions at other operating plants that are applicable at Dresden and Quad Cities and maintain necessary levels of system, component or parameter readability, the proposed changes do not involve a significant reduction in the margin of safety.

The proposed amendment for Quad Cities Station will not reduce the availability of systems associated with the Plant Systems when required to mitigate accident conditions; therefore, the proposed changes do not involve a significant reduction in the margin of safety.

ATTACHMENT 6 ENVIRONMENTAL ASSESSMENT STATEMENT APPLICABILITY REVIEW Commonwealth Edison has evaluated the proposed amendment against the criteria for the identification of licensing and regulatory actions requiring environmental assessment in accordance with 10 CFR 51.20. It has been determined that the proposed changes meet the criteria for a categorical exclusion as provided under 10 CFR 51.22 (c)(9). This conclusion has been determined because the changes requested do not pose significant hazards consideration or do not involve a significant increase in the amounts, and no significant changes in the types, of any effluent that may be released off site. Additionally, this request does not involve a significant increase in individual or cumulative occupational radiation exposure. Therefore, the Environmental Assessment Statement is not applicable for these changes.

ATTACHMENT 7 GENERIC LETTER 87-09 IMPLEMENTATION Technical Specification 3/4.8 "PLANT SYSTEMS II l

ATTACHMENT 7 DRESDEN APPLICATION OF GENERIC LETTER 87-09 REVISION TO SPECIFICATION 3.0.D The Dresden/Quad Cities Technical Specification Upgrade Program has implemented the recommendations of Generic Letter 87-09. Included in these recommendations was a revision to Standard Technical Specification 3.0.4 for which these stations had no corresponding restriction. Under the proposed Specification, entry into an operational mode or other specified condition is permitted under compliance with the Action requirements. Indicated below is the method of implementation for this recommendation for each Action requirement in this package.

PROPOSED ACTION APPL.

CONT. OPS IN TECH SPEC (D/QC)

MOD Es APP. COND?

CAT CLARIFICATION 3/4.8 3.8.A 1.a 1-3 30 days NO Does not allow unlimited cont. ops.

1.b 1-3 7 days NO Does not allow unlimited cont. ops.

1.c 1-3 72 hrs NO Does not allow unlimited cont. ops.

1.d 1-3 8 hrs NO Does not allow unlimited cont. ops.

-12 3&4 UNLIMITED OK No mode changes required by this Specification.

2/3 4&5 UNLIMITED OK No mode changes required by this Specification.

-/4 5

UNLIMITED OK No mode changes required by this Specification.

3.8.B w/EDG UNLIMITED OK No mode changes required by this Specification.

3.8.C 1

1-3 0 hrs NO Does not allow unlimited cont. ops.

2 4&5 UNLIMITED OK No mode changes required by this Specification.

3 UNLIMITED OK No mode changes required by this Specification.

PROPOSED ACTION APPL.

CONT.OPS IN TECH SPEC (D/QC)

MODEs APP. COND?

CAT CLARIFICATION 3/4.8 3.8.D 1

1-3 14 days NO Does not allow unlimited cont. ops.

2 4&5 UNLIMITED OK No mode changes required by this Specification.

2 UNLIMITED NO Must exit applicable modes.

3.8.E 1

AAT 12 hrs NO Does not allow unlimited cont. ops.

2 AAT 0 hrs NO Does not allow unlimited cont. ops.

3.8.F 1-5 UNLIMITED OK No mode changes required by this Specification.

3.8.G 1

AAT 0 hrs OK No mode changes required by this Specification.

2 AAT ANNUAL OK No mode changes required by this Specification.

3 AAT UNLIMITED OK No mode changes required by ttiis Specification.

3.8.H Sys Ops UNLIMITED OK No mode changes required by this Specification.

3.8.1 1-3#

UNLIMITED OK No mode changes required by this Specification.

3.8.J (D only)

AAT UNLIMITED OK No mode changes required by this Specification.

ML17179B076

Text

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