Text

Developmental Revision B - Technical Requirements Manual TR 3.7 - Plant Systems
	ML100550626
Person / Time
Site:	Watts Bar
Issue date:	02/02/2010
From:	; Tennessee Valley Authority
To:	; Office of Nuclear Reactor Regulation
References
	Download: ML100550626 (23)
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Steam Generator Pressure/Temperature Limitations TR 3.7.1 Watts Bar - Unit 2 3.7-1 Technical Requirements (developmental)

A TR 3.7 PLANT SYSTEMS TR 3.7.1 Steam Generator Pressure/Temperature Limitations TR 3.7.1 The pressure of the reactor and secondary coolants in the Steam Generators shall be 200 psig.

APPLICABILITY:

Whenever the temperature of the reactor or secondary coolant in any Steam Generator 70°F.

NOTE----------------------------------------------

While this TR is not met, decreasing the temperature of the coolant in the primary or secondary of any steam generator to 70°F is not permitted.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

NOTE--------------

All Required Actions must be completed whenever this Condition is entered.

Steam Generator pressure not within limits.

A.1 Reduce pressure to 200 psig.

30 minutes AND A.2 Perform an engineering evaluation to determine the effect of the over-pressurization on the structural integrity of the Steam Generator.

Prior to increasing Steam Generator coolant temperatures to > 200°F AND A.3 Determine that the Steam Generator remains acceptable for continued operation.

Prior to increasing Steam Generator coolant temperatures to > 200°F

Steam Generator Pressure/Temperature Limitations TR 3.7.1 Watts Bar - Unit 2 3.7-2 Technical Requirements (developmental)

A TECHNICAL SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.7.1.1 Determine that the pressure of the reactor and the secondary coolants in the Steam Generators is

< 200 psig.

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

Flood Protection Plan TR 3.7.2 Watts Bar - Unit 2 3.7-3 Technical Requirements (developmental)

B TR 3.7 PLANT SYSTEMS TR 3.7.2 Flood Protection Plan TR 3.7.2 The flood protection plan shall be ready for implementation to maintain the plant in a safe condition.

APPLICABILITY:

When one or more of the following conditions exist:

a.

Extreme flood-producing rainfall conditions in the east Tennessee watershed, or

b.

Receipt of notification from River Operations (RO) that predicted flood levels based on rainfall on the ground or potential failure problems with one or more dams combined with critical headwater elevations and flood-producing rainfall may result in subsequent issuance of a Stage I flood warning.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Stage I flood warning issued.

A.1 Be in at least MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND A.2 Initiate and complete the Stage I flood protection plan. Completion not required if flood warning is retracted by RO.

10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months AND A.3 Establish a SDM 5% k/k and Tavg 350°F.

10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months AND (continued)

Flood Protection Plan TR 3.7.2 Watts Bar - Unit 2 3.7-4 Technical Requirements (developmental)

B ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.4.1 Verify that communications between the TVA RO and the Watts Bar Nuclear Plant have been established.

10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months OR A.4.2 Initiate and complete the Stage II flood protection procedure. Completion is not required if flood warning is retracted by RO.

27 hours3.125e-4 days 0.0075 hours 4.464286e-5 weeks 1.02735e-5 months B.

Stage II flood warning issued.

B.1 Initiate and complete the Stage II flood protection plan. Completion is not required if flood warning is retracted by RO.

17 hours1.967593e-4 days 0.00472 hours 2.810847e-5 weeks 6.4685e-6 months OR Prior to flooding of the site TECHNICAL SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.7.2.1

NOTE-------------------------------

Only required when one of the applicability criteria is met.

Establish and maintain communications between Watts Bar Nuclear Plant and TVA RO Group.

3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months

Snubbers TR 3.7.3 Watts Bar - Unit 2 3.7-5 Technical Requirements (developmental)

A TR 3.7 PLANT SYSTEMS TR 3.7.3 Snubbers TR 3.7.3 All snubbers utilized on safety related systems shall be OPERABLE. For those snubbers utilized on non-safety related systems, each snubber shall be OPERABLE if a failure of that snubber or the failure of the non-safety related system would have an adverse effect on any safety related system.

APPLICABILITY:

MODES 1, 2, 3, and 4.

MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more snubber(s) inoperable.

A.1.1 Restore snubber(s) to OPERABLE status.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR A.1.2 Replace snubber(s).

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND A.2 Perform an engineering evaluation per Table 3.7.3-5 on the attached component.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR A.3 Perform an engineering evaluation demonstrating OPERABILITY of the supported system.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B.

Required Action and associated Completion Time not met.

B.1 Declare supported component or supported system inoperable.

Immediately

Snubbers TR 3.7.3 Watts Bar - Unit 2 3.7-6 Technical Requirements (developmental)

A TECHNICAL SURVEILLANCE REQUIREMENTS

NOTES-----------------------------------------------------------

1.

Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program.

2.

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 results 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.

3.

As used herein, type of snubber shall mean snubbers of the same design and manufacturer, irrespective of capacity.

SURVEILLANCE FREQUENCY TSR 3.7.3.1 Visually inspect each snubber in accordance with the acceptance criteria in Table 3.7.3-1.

In accordance with Table 3.7.3-2 TSR 3.7.3.2 Perform a transient event inspection of all hydraulic and mechanical snubbers in accordance with Table 3.7.3-3.

6 months following transient event TSR 3.7.3.3 Perform a functional test on a representative sample of snubbers in accordance with Table 3.7.3-4 to determine acceptance with criteria in Table 3.7.3-5.

Each refueling outage (continued)

Snubbers TR 3.7.3 Watts Bar - Unit 2 3.7-7 Technical Requirements (developmental)

B TECHNICAL SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.7.3.4

NOTES-----------------------------

1.

The maximum expected service life for various seals, springs, and other critical parts shall be determined and established based on engineering information and shall be extended or shortened based on monitored test results and failure history.

2.

Critical parts shall be replaced so that the maximum service life will not be exceeded during a period when the snubber is required to be OPERABLE.

3.

The parts replacement shall be documented and the documentation shall be retained for the duration of the unit operating license.

Verify that the service life of hydraulic and mechanical snubbers has not been exceeded or will not be exceeded prior to the next scheduled surveillance inspection.

Each refueling outage

Snubbers TR 3.7.3 Watts Bar - Unit 2 3.7-8 Technical Requirements (developmental)

A Table 3.7.3-1 (Page 1 of 1)

Snubber Visual Inspection Acceptance Criteria

1. Visual inspection shall verify that:

a. There are no visible indications of damage or impaired OPERABILITY;

b. Attachments to the foundation or supporting structure are functional; and

c. Fasteners for attachment of the snubber to the component and to the snubber anchorage are functional.

2. Snubbers which appear inoperable as a result of visual inspections shall be classified as unacceptable and may be reclassified acceptable for the purpose of establishing the next visual inspection interval, provided that:

a. 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

b. The affected snubber is functionally tested in the as-found condition and determined OPERABLE per Table 3.7.3-5, Snubber Functional Testing Acceptance Criteria.

3. All snubbers connected to an inoperable common hydraulic fluid reservoir shall be counted as unacceptable for determining the next inspection interval.

4. Snubbers which have been made inoperable as the result of unexpected transients, isolated damage or other such random events, when the provisions of Table 3.7.3-3 have been met and any other appropriate corrective action implemented, shall not be counted in determining the next visual inspection interval.

5. 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 TR 3.7.3 Watts Bar - Unit 2 3.7-9 Technical Requirements (developmental)

A Table 3.7.3-2 (Page 1 of 2)

Snubber Visual Inspection Surveillance Frequency NUMBER OF UNACCEPTABLE SNUBBERS Population or Category (Notes 1 and 2)

Column A Extended Interval (Notes 3 and 6)

Column B Repeat Interval (Notes 4 and 6)

Column C Reduce Interval (Notes 5 and 6) 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 or greater 29 56 109 Note 1:

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 licensee must make and document that decision before any inspection and shall use that decision as the basis upon which to determine the next inspection interval for that category.

Note 2:

Interpolation between population or category size 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 described by interpolation.

(continued)

Snubbers TR 3.7.3 Watts Bar - Unit 2 3.7-10 Technical Requirements (developmental)

A Table 3.7.3-2 (Page 2 of 2)

Snubber Visual Inspection Surveillance Frequency Note 3:

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.

Note 4:

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.

Note 5:

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.

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.

Note 6:

The provisions of TSR 3.0.2 are applicable for all inspection intervals up to and including 48 months.

Snubbers TR 3.7.3 Watts Bar - Unit 2 3.7-11 Technical Requirements (developmental)

A Table 3.7.3-3 (Page 1 of 1)

Snubber Transient Event Inspection

1. An inspection shall be performed of all hydraulic and mechanical snubbers attached to sections of systems that have experienced unexpected, potentially damaging transients as determined from a review of operational data and a visual inspection of the systems within six months following such an event.

2. In addition to satisfying the visual inspection acceptance criteria, freedom-of-motion of mechanical snubbers shall be verified using one of the following:

a. Manually induced snubber movement;

b. Evaluation of in-place snubber piston setting; or

c. Stroking the mechanical snubber through its full range of travel.

Snubbers TR 3.7.3 Watts Bar - Unit 2 3.7-12 Technical Requirements (developmental)

A Table 3.7.3-4 (Page 1 of 2)

Snubber Functional Testing Plan

1. The representative sample of snubbers shall include each type and shall be tested using Sample Plan A for hydraulic snubbers and Sample Plan B for mechanical snubbers.

2. The NRC Regional Administrator shall be notified in writing of any changes to the sample plan prior to the test period.

SAMPLE PLAN A

1. At least 10% of the total hydraulic snubber population shall be functionally tested either in-place or in a bench test.

2. For each hydraulic snubber of a type that does not meet the functional test acceptance criteria of Table 3.7.3-5, an additional 10% of hydraulic snubbers shall be functionally tested until no more failures are found or until all hydraulic snubbers have been functionally tested.

SAMPLE PLAN B

1. An initial representative sample of 37 mechanical snubbers shall be functionally tested in accordance with Figure 3.7.3-1. For each mechanical snubber type which does not meet the functional test acceptance criteria of Table 3.7.3-5, another sample of at least 19 snubbers shall be tested. The results from this sample plan shall be plotted using an "Accept" line which follows the equation N = 36.49 + 18.18C. If the point plotted falls on or below the "Accept" line, testing of that type of snubber may be terminated. If the point plotted falls above the "Accept" line, testing must continue until the point falls in the "Accept" region or all mechanical snubbers have been tested.

(continued)

Snubbers TR 3.7.3 Watts Bar - Unit 2 3.7-13 Technical Requirements (developmental)

A Table 3.7.3-4 (Page 2 of 2)

Snubber Functional Testing Plan TABLE NOTES

1. 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 provided all snubbers tested with the failed equipment during the day of equipment failure are retested.

2. 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 practicable, that they are representative of the various configurations, operating environments, range of size, and capacity of snubbers of each type.

3. 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.

4. If during the functional testing, additional sampling is required due to failure of only one type of snubber, the functional test results shall be reviewed at that time to determine if additional samples should be limited to the type of snubber which has failed the functional testing.

5. Administrative controls are required for snubber removal for functional surveillance testing during plant operating Modes 1 through 4.

Snubbers TR 3.7.3 Watts Bar - Unit 2 3.7-14 Technical Requirements (developmental)

A Table 3.7.3-5 (Page 1 of 1)

Snubber Functional Testing Acceptance Criteria The snubber functional test shall verify that:

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

b. Snubber bleed, or release rate where required, is present in both tension and compression, within the specified range (Hydraulic Snubbers).

c. The force required to initiate or maintain motion of the snubber is within the specified range in both directions of travel (Mechanical Snubbers).

TABLE NOTES

1. 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.

2. An engineering evaluation shall be made of each failure to meet the functional test criteria to determine the cause of the failure. The results of this evaluation shall be used, if applicable, in selecting snubbers to be tested in an effort to determine the OPERABILITY of other snubbers irrespective of the type which may be subject to the same failure mode.

3. For 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.

4. 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 Table 3.7.3-4 for snubbers not meeting the functional test acceptance criteria.

Snubbers TR 3.7.3 Watts Bar - Unit 2 3.7-15 Technical Requirements (developmental)

A 0

1 6

3 4

5 2

30 40 50 100 60 70 80 90 110 120 130 C

Continue testing region N = 36.49 + 18.18C Accept region N

N =

Total number of snubbers tested C =

Number of snubbers which do not meet functional test acceptance criteria FIGURE 3.7.3-1 Sample Plan B for Snubber Functional Test

Sealed Source Contamination TR 3.7.4 Watts Bar - Unit 2 3.7-16 Technical Requirements (developmental)

A TR 3.7 PLANT SYSTEMS TR 3.7.4. Sealed Source Contamination TR 3.7.4.

The removable contamination shall be < 0.005 microcuries for each sealed source containing radioactive material > 100 microcuries of beta and/or gamma emitting material or > 5 microcuries of alpha emitting material.

APPLICABILITY:

At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Sealed source contamination not within limit.

NOTE-------------------

TR 3.0.3 is not applicable.

A.1 Remove sealed source from use.

Immediately AND A.2.1 Decontaminate and repair sealed source.

Prior to returning the sealed source to use.

OR A.2.2 Dispose of sealed source in accordance with NRC regulations.

In accordance with NRC regulations.

Sealed Source Contamination TR 3.7.4 Watts Bar - Unit 2 3.7-17 Technical Requirements (developmental)

A TECHNICAL SURVEILLANCE REQUIREMENTS

NOTES-------------------------------------------------------------

1. The licensee, other persons specifically authorized by the NRC, or an Agreement State shall perform the Technical Surveillance Requirements.

2. The test methods shall have a detection sensitivity of 0.005 microcuries per test sample.

SURVEILLANCE FREQUENCY TSR 3.7.4.1

NOTES-----------------------------

1. Only applicable to sources in use.

2. Only applicable to sources with half-lives

> 30 days, excluding Hydrogen 3.

3. Not applicable to startup sources and fission detectors previously subjected to core flux.

4. Only applicable to sources in any form other than gas.

Determine that the removable contamination is

< 0.005 microcuries for each sealed source.

6 months TSR 3.7.4.2

NOTES-----------------------------

1. Only applicable to sources not in use.

2. Sealed sources and fission detector transferred without a certificate indicating the last test date shall be tested prior to being placed in use.

Determine that the removable contamination is

< 0.005 microcuries for each sealed source and fission detector.

Within 6 months prior to use or transfer to another licensee (continued)

Sealed Source Contamination TR 3.7.4 Watts Bar - Unit 2 3.7-18 Technical Requirements (developmental)

A TECHNICAL SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY TSR 3.7.4.3

NOTE------------------------------

Only applicable to startup sources and incore fission detectors not in use.

Determine that the removable contamination is

< 0.005 microcuries for each startup source and incore fission detector.

Within 31 days prior to being installed AND Following repair or maintenance to the source TSR 3.7.4.4

NOTE------------------------------

Only applicable to excore fission detectors.

Determine that the removable contamination is

< 0.005 microcuries for each excore fission detector.

Within 31 days prior to being installed AND Following repair or maintenance to the source

Area Temperature Monitoring 3.7.5 Watts Bar - Unit 2 3.7-19 Technical Requirements (developmental)

A TR 3.7 PLANT SYSTEMS TR 3.7.5 Area Temperature Monitoring TR 3.7.5 The normal temperature limit of each area shown in Table 3.7.5-1 shall not be exceeded for > 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and the abnormal temperature limits shall not be exceeded.

APPLICABILITY:

Whenever the affected equipment in an area is required to be OPERABLE.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more areas exceeding normal temperature limits for

> 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

A.1

NOTE------------

TR 3.0.3 is not applicable.

Document in accordance with the Corrective Action Program and include a record of the cumulative time and the amount by which the temperature in the affected area(s) exceeded the limit(s) and an analysis to demonstrate OPERABILITY of the affected equipment.

In accordance with the Corrective Action Program (continued)

Area Temperature Monitoring 3.7.5 Watts Bar - Unit 2 3.7-20 Technical Requirements (developmental)

A ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.

One or more areas exceeding abnormal temperature limits except for the IPS Mechanical or Electrical Equipment Rooms (Areas 31, 32, or 34).

B.1.1 Restore the area(s) to within normal temperature limits.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months OR B.1.2 Declare the affected equipment in the affected area(s) inoperable.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months AND B.2 Document in accordance with the Corrective Action Program and include a record of the cumulative time and the amount by which the temperature in the affected area(s) exceeded the limit(s) and an analysis to demonstrate OPERABILITY of the affected equipment.

In accordance with the Corrective Action Program C.

Mechanical or Electrical Equipment Rooms in Intake Pumping Station (Areas 31, 32, or 34) less than 40°F and greater than 32°F.

C.1 Initiate action to maintain temperatures greater than 32°F.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND C.2 Restore temperatures to within normal limits.

7 days (continued)

Area Temperature Monitoring 3.7.5 Watts Bar - Unit 2 3.7-21 Technical Requirements (developmental)

A ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D.

Mechanical or Electrical Equipment Rooms in Intake Pumping Station (Areas 31, 32, or 34) 32°F or less.

D.1 Declare the affected equipment in the affected area(s) inoperable.

Immediately AND D.2 Document in accordance with the Corrective Action Program and include a record of the cumulative time and the amount by which the temperature in the affected area(s) exceeded the limit(s) and an analysis to demonstrate OPERABILITY of the affected equipment.

In accordance with the Corrective Action Program TECHNICAL SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.7.5.1 Verify each area temperature is within limits.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

Area Temperature Monitoring 3.7.5 Watts Bar - Unit 2 3.7-22 Technical Requirements (developmental)

B Table 3.7.5-1 (Page 1 of 2)

Area Temperature Monitoring AREA NORMAL LIMIT

(°F)

ABNORMAL LIMIT

(°F)

1.

Aux Bldg el 772 next to 480V Sd Bd transformer 1A2-A.

104 110

2.

Aux Bldg el 772 next to 480V Sd Bd transformer 1B1-B.

104 110

3.

Aux Bldg el 772 next to 480V Sd Bd transformer 2A2-A.

104 110

4.

Aux Bldg el 772 next to 480V Sd Bd transformer 2B2-B.

104 110

5.

Aux Bldg el 772 next to 480V Rx MOV Bd 1A2-A.

83 104

6.

Aux Bldg el 772 next to 480V Rx MOV Bd 2A2-A.

83 104

7.

Aux Bldg el 772 next to 480V Rx MOV Bd 2B2-B.

83 104

8.

Aux Bldg el 772 across from spare 125V vital battery charger 1-S.

83 104

9.

Aux Bldg el 772 U1 Mech Equip Room.

91 104

10.

Aux Bldg el 757 U1 Sd Bd room behind stairs S-A3.

85 104

11.

Aux Bldg el 757 U2 Sd Bd room behind stairs S-A13.

85 104

12.

Aux Bldg el 757 U1 Refueling beside Aux boration makeup tk.

104 115

13.

Aux Bldg el 737 U1 outside supply fan room.

104 110

14.

Aux Bldg el 713 U1 across from AFW pumps.

104 110

15.

Aux Bldg el 692 U1 outside AFW pump room door.

104 110

16.

Aux Bldg el 692 U2 near boric acid concentrate filter vault.

104 110

17.

Aux Bldg el 676 next to O-L-629.

104 110

18.

North steam valve vault room U1. (at affected MSSVs) 50 50

19.

South steam valve vault room U1. (at affected MSSVs) 50 50 (continued)

Area Temperature Monitoring 3.7.5 Watts Bar - Unit 2 3.7-23 Technical Requirements (developmental)

B Table 3.7.5-1 (Page 2 of 2)

Area Temperature Monitoring AREA NORMAL LIMIT

(°F)

ABNORMAL LIMIT

(°F)

20.

Add Equip Bldg U1 el 729 between UHI accumulators.

92 110

21.

CB Main Control Room south wall.

80 104

22.

CB Main Control Room across from 1-M-9.

80 104

23.

CB Computer room el 708 center of room.

74 104

24.

CB Aux. Instrument Room el 708.

90 104

25.

D/G Bldg el 742 2B-B D/G room on wall by battery charger.

104 120

26.

D/G Bldg el 742 1A-A D/G Room near D/G set.

50 50

27.

D/G Bldg el 742 1B-B D/G Room near D/G set.

50 50

28.

D/G Bldg el 742 2A-A D/G Room near D/G set.

50 50

29.

D/G Bldg el 742 2B-B D/G Room near D/G set.

50 50

30.

D/G Bldg el 760.5 next to 480V diesel Aux Bd 2B1-B.

104 120

31.

IPS Mechanical Equipment Room 1 el 722 near ERCW and HPFP Instruments and sense lines.

50 104 40 115

32.

IPS Mechanical Equipment Room 2 el 722 near ERCW and HPFP Instruments and sense lines.

50 104 40 115

33.

IPS el 741 in B train ERCW pump room.

120 120

34.

IPS el 711 next to 480V IPS board and transformer (A bus).

50 104 40 115

35.

IPS el 711 next to 480V IPS board and transformer (B bus).

104 115

36.

Add D/G Bldg el 742 C-S D/G Room near D/G set.

50 50

ML100550626

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