ML20196C511

Proposed Tech Specs,Clarifying Axial Flux Difference Requirements Between 15% & 50% Rated Thermal Power,Deleting BV-1 Blank Page 3/4 3-16 & Renumbering Page 3/4 3-16a

ML20196C511
Person / Time
Site:	Beaver Valley
Issue date:	02/05/1988
From:	DUQUESNE LIGHT CO.
To:
Shared Package
ML20196C489	List: ML20196C487 ML20196C495 ML20196C511
References
NUDOCS 8802160127
Download: ML20196C511 (12)

Text

.

ATTACHMENT A-1 Revise the Beaver Valley Unit No. 1 Technical Specifications as follows:

Remove Pages Insert Pages 3/4 2-2 3/4 2-2 3/4 3-16 3/4 3-16 3/4 3-16a 3/4 4-10a 3/4 4-10a 6-23 6-23 i

AD PDN P

POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION (Continued) b.

THERMAL POWER shall not be increased above 90% of RATED THERMAL POWER unless the indicated AFD is within the + 7%

target band and ACTION a.2.a) 1), above has been satisfied.

I c.

THERMAL POWER shall not be increased above 50% of RATED THERMAL POWER unless the indicated AFD has not been outside of the 1

7%

target band for more than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> penalty deviation cumulative during the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SUkVEILLANCE REQUIREMENTS 4.2.1.1 The indicated AXIAL FLUX DIFFERENCE shall be determined to 1

within its limits during POWER OPERATION above 15% of RATED

.HERMAL POWER by:

a.

Monitoring the indicated AFD for each OPERABLE excore l

channel:

1 1.

At least once per 7 days when the AFD Monitor Alarm is OPERABLE, and 2.

At least once per hour for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after restoring the AFD Monitor Alarm to OPERABLE status.

b.

Monitoring and logging the indicated AXIAL FLUX DIFFERENCE for each OPERABLE excore channel at least once per hour for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and at least once per 30 minutes thereafter, when the AXIAL FLUX DIFFERENCE Monitor Alarm is inoperable.

The logged values of the indicated AXIAL FLUX DIFFERENCE shall be assumed to exist during the interval preceding each logging.

4.2.1.2 The indicated AFD shall be considered outside of its + 7%

target band when at least 2 of 4 or 2 of 3 OPERABLE excore channels are indicating the AFD to be outside the target band.

POWER OPERATION outside of the 1 7% target band shall be accumulated on a time basis of:

a.

One minute penalty deviation for each one minute of POWER OPERATION outside of the target band at THERMAL POWER levels equal to or above 50% of RATED THERMAL POWER, and b.

One-half minute penalty deviation fer each one minute of POWER OPERATION outside of the target band at THERMAL POWER levels between 15% and 50% of RATED THERMAL POWER.

l BEA/ER VALLEY - UNIT 1 3/4 2-2 PROPOSED WORDING

TABLE 3.3-3 (Continued) to M

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION tnw t*y MINIMUM K

TOTAL NO.

CHANNNELS CHANNELS APPLICABLE i

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION Czy 1.1 SAFETY INJECTION-TRANSFER FROM INJECTION TO THE RE-g CIRCULATION MODE a.

Manual Initiation 2 sets I set 2 sets 1, 2, 3, 4 18 yx 2 switches /

Om set Ow v3 %

Mh U w b.

Automatic Actuation 2

1 2

1,2,3 18

@5 Logic Coincident Wm with Safety Injection 8

Signal ZO c.

Refueling Water Storage 4

2 3

1,2,3 16 Tank Level-Low d.

Refueling Water Storage 1 per 1 per 1 per 1, 2, 3 18 Tank Level - Auto QS train train train Flow Reduction i

t L

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4 5.

Defect means an imperfection of such severity that it exceeds the plugging limit.

A tube containing a defect is defective.

Any tube which does not permit the passage of the oddy-current inspection probe shall be deemed a defective tube.

6.

Plugging Limit means the imperfection depth at or beyond which the tube shall be removed from service because it may become unserviceable prior to the next inspection and is equal to 40% of the nominal tube wall thickness.

7.

Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural integrity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feedwater line break as specified in 4.4.5.3.c, above.

8.

Tube Inspection means an inspection of the steam generator tube from the point of entry (hot leg side) completely around the U-bend to the top support to the cold leg.

b.

The steam generator shall be determined OPERABLE after completing the corresponding actions (plug all tubes exceeding the plugging limit and all tubes containing through-wall cracks) required by Tabic 4.4-2.

4.4.5.5 Reports a.

Within 15 days following the completion of each inservice inspection of steam generator

tubes, the number of tubes plugged in each steam generator shall be reported to the Commission in a

Special Report pursuant to Specification 6.9.2.

b.

The complete results of the steam generator tube inservice inspection shall be submitted to the Commission in a Special Report pursuant to Specification 6.9.2 within 12 months I

following the completion of the inspection.

This Special Report shall include:

1.

Number and extent of tubes inspected.

2.

Location and percent of wall-thickness penetration for cach indication of an imperfection.

3.

Identification of tubes plugged.

BEAVER VALLEY - UNIT 1 3/4 4-10a PROPOSED WORDING 1

ADMINISTRATIVE CONTROLS a.

ECCS Actuation, Specifications 3.5.2 and 3.5.3.

b.

Inoperable seismic Monitoring Instrumentation, Specification 3.3.3.3.

c.

Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.4.

d.

Seismic event analysis, Specification 4.3.3.3.2.

c.

Scaled source leakage in excess of limits, Specification 4.7.9.1.3.

f.

Fire Detection Instrumentation, Specification 3.3.3.6.

g.

Fire Suppression Systems, Specifications 3.7.14.1, 3.7.14.2 and 3.7.14.3 and 3.7.14.5.

h.

Miscellaneous reporting requirements specified in the Action Statements for Radiological Effluent Technical Specifications, i.

Containment Inspection Report, Specification 4.6.1.6.2.

l l

j.

Steam Generator Tube Inservice Inspection Results Report, l

Specification 4.4.5.5.

l 6.10 RECORD RETENTION l

i 6.10.1 The following records shall be retained for at least five (5) years:

a.

Records and logs of facility operation covering time interval at each power level, b.

Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.

l c.

All Reportable Events, d.

Records of surveillance activities, inspections and calibrations required by these Technical Specifications.

c.

Records of reactor tests and experiments, f.

Records of changes made to Operating Procedures.

g.

Records of radioactive shipments.

h.

Records of sealed source leak tests and results, i.

Records of annual physical inventory of all scaled source material of record.

BEAVER VALLEY - UNIT 1 6-23 PROPOSED WORDING

~

ATTACHMENT' A-2 Revise the Beaver Valley Unit No. 2 Technical Specifications as follows:

i i

Remove Pages Insert Pages 3/4 2-2 3/4.2-2 3/4 4-14 3/4 4-14 k

L a

P P

n

[

l t

i i

i

)

4 4

...--.--,.,,.,.,n,...-.

-=--

. ~ - - -,

POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION (Continued)

ACTION:

(Continued) b.

THERMAL POWER shall not be increased above 90% of RATED THERMAL POWER unless the indicated AFD is within the + 7 percent target band and ACTION a.2.a) 1), above has been satisfied.

c.

THERMAL POWER shall not be increased' above 50% of RATED THERMAL POWER unless the indicated AFD has not been outside of the 1 7%

target band for more than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> penalty deviation cumulative during the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.2.1.1 The indicated AXIAL FLUX DIFFERENCE shall be determined to be within its limits during POWER OPERATION above 15% of RATED THERMAL POWER by:

a.

Monitoring the indicated AFD for each OPERABLE excore channel:

1.

At least once per 7 days when the AFD Monitor Alarm is OPERABLE, and 2.

At least once por hour for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after restoring the AFD Monitor Alarm to OPERABLE status.

b.

Monitoring and logging the indicated AXIAL FLUX DIFFERENCE for each OPERABLE excore channel at least once per hour for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and at least once per 30 minutes thereafter, when the AXIAL FLUX DIFFERENCE Monitor Alarm is inoperable.

The logged values of the indicated AXIAL FLUX DIFFERENCE shall be assumed to exist during the interval preceding each logging.

j 4.2.1.2 The indicated AFD shall be considered outside of its + 7%

target band when at least 2 of 4 or 2 of 3 OPERABLE excore channels are indicating the AFD to be outside the target band.

POWER OPERATION outside of the 1 7% target band shall be accumulated on a

]

time basis of:

j a.

One minute penalty deviation for each one minute of POWER OPERATION outside of the target band at THERMAL POWER levels equal t o or above 50% of RATED THERMAL POWER, and b.

One-half minute penalty deviation for each one minute of POWER OPERATION outside of the target band at THERMAL POWER levels between 15% and SO%.

l BEAVER VALLEY - UNIT 2 3/4 2-2 PROPOSED WORDING

e REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 7.

Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural integrity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feedwater line break as specified in 4.4.5.3.c, above.

8.

Tube Inspection means an inspection of the steam generator tube from the point of entry (hot leg side) completely around the U-bend to the top support of the cold leg.

b.

The steam generator shall be determined. OPERABLE after completing the corresponding actions (plug all tubes exceeding the plugging limit and all tubes containing through-wall cracks) required by Table 4.4-2.

4.4.5.5 Reports a.

Within 15 days following the completion of each inservice inspection of steam generator

tubes, the number of tubes plugged in each steam generator shall be reported to the Commission in a

Special Report pursuant to Specification 6.9.2.

b.

The complete results of the steam generator tube inservice inspection shall be submitted to the Commission in a special Report pursuant to Specification 6.9.2 within 12 months following the completion of the inspection.

This Special Report shall include:

l.

Number and extent of tubes inspected.

2.

Location and percent of wall-thickness penetration for each indication of an imperfection.

3.

Identification of tubes plugged, c.

Results of steam generator tube inspections which fall into Category C-3 shall be reported to the Commission pursuant to specification 6.6 prior to resumption for plant operation.

The written report shall provide a

description of investigations conducted to determine the cause of the tube degradation and corrective measures taken to prevent recurrence.

BEAVER VALLEY - UNIT 2 3/4 4-14 PROPOSED WORDING

4 ATTACHMENT B Safety Analysis Beaver Valley Power Station Proposed Technical Specification Change Unit 1 Change No. 148 Unit 2 Change No. 3 Description of amendment request:

The proposed amendment would incorporate the following administrativo changes:

1.

Page 3/4 2-2 for BV-1 and BV-2, surveillance requirement 4.2.1.2.b is being revised to clarify the one-half minute penalty deviation for Axial Flux Difference.(AFD) requirements between 15%

and 50%

Rated Thermal Power (RTP) to reflect the basis for this specification described in the bases and the Standard Technical Specification (STS).

BV-1 and BV-2 surveillance requirement 4.2.1.2.b states:

One half minute penalty deviation for each one minute of POWER OPERATION outside of the target band at THERMAL POWER levels below 50%

of RATED THERMAL POWER.

STS surveillance requirement 4.2.1.2.b states:

One-half minute penalty deviation for each 1 minute of POWER OPERATION outside of the target band at THERMAL POWER levels between 15%

and 50%

of RATED THERMAL POWER.

BV-1 and BV-2 and STS Bases states:

For THERMAL POWER levels between 15%

and 50%

of RATED THERMAL POWER, deviations of the AFD outside of the target band are less significant.

The penalty of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> actual time reflects this reduced significance.

Therefore, surveillance requirement 4.2.1.2.b will be replaced in the BV-1 and BV-2 technical specifications by STS surveillance requirement 4.2.1.2.b to provide consistency with the bases and the STS.

This is an administrative change and will not affect the BV-1 FSAR, the BV-2 FSAR or any regulatory basis.

2)

Page 3/4 3-16a, page 3/4 3-16 is being deleted from the BV-1 technical specifications since this is a blank page, therefore, page 3/4 3-16a will be re-numbered to 3/4 3-16.

This is an editorial change and will not affect the BV-1 FSAR or any regulatory basis.

O ATTACHMENT B Page 2 3)

Page 3/4 4-10a for BV-1 surveillance requirement 4.4.5.5.a and 4.4.5.5.b will be revised to require reporting the steam generator tube inspection results to the Commission in a Special Report.

Page 3/4 4-4 for BV-2, Surveillance Requirement 4.4.5.5.a will be revised to require reporting the steam generator tube inspection results to the Commission in a Special Report.

BV-1 and BV-2 surveillance requirement 4.4.5.5.a currently requires reporting within 15 days but does not state the type of report required.

BV-1 surveillance requirement 4.4.5.5.b currently requires reporting in accordance with the Annual Operating Report which is no longer provided.

To clarify the reporting requirements for steam generator tube inservice inspection

results, these surveillance requirements will be replaced with 4.4.5.5.a and 4.4.5.5.b from the STS which requires reporting the steam generator tube inservice inspection results to the Comraission in a Special Report.

This is an administrative change and will not affect the BV-1

FSAR, the BV-2 FSAR or any regulatory basis.

4)

Page 6-23 for BV-1 administrative control section 6.9.2 will be revised by adding item j,

Steam Generator Tube Inservice Inspection

Report, to the list of Special Reports.

This is consistent with BV-2 Section 6.9.2.

This reflects the change to page 1/4 4-10a for BV-1 and page 3/4 4-14 for BV-2 which incorpocates the STS special reporting requirements.

This is an administrative change and will not affect the BV-1 ~FSAR, the BV-2 FSAR or any regulatory basis.

ATTACHMENT C No Significant Hazards Evaluation Beaver Valley Power Station Proposed Technical Specification Change Unit 1 Change No. 148 Unit 2 Change No. 3 Basis for no significant hazards consideration determination:

The Commission has provided standards for determining whether a significan:

hazards consideration exists (10 CFR 50.92(c)).

A proposed amendment to an operating license for a facility 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; (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 hazards 1

consideration because:

1)

Surveillance requirement 4.2.1.2.b is being revised to reflect the STS to clarify the AFD requirements between 15% and 50% RTP.

Page 3/4 3-16a for BV-1 is being re-numbered with page number 3/4 3-16 since this is currently a blank page and can be deleted.

Surveillance requirement 4.4.5.5.a and 4.4.5.5.b are being revised to reflect the STS reporting requirements for steam generator tube inspection results.

Item j for BV-1 and Item k for BV-2 is being added to administrative control section 6.9.2 i'

to include the special report for steam generator tube inspection results.

These are administrative changes that will not affect the FSAR system descriptions or accident analyses and therefore will not involve a

significant increase in the probability or consequences of an accident previously evaluated.

2)

These changes are administrative in nature since only clarification is provided to reflect the STS and no change to equipment or components or the FSAR accident analysis is required.

Thus, no adverse safety considerations are introduced by the proposed changes.

Therefore, the probability for an accident or a

malfunction of a different type than previously evaluated will not be created.

3)

The proposed changes provide clarification of the AFD surveillance requirements between 15% and 50% RTP and reflect the STS reporting requirements for steam generator tube inspection results.

These changes are consistent with the technical specification bases and will not affect any safety analysis or design basis which would involve a significant reduction in the margin of safety.

1 4

.l

~~ ATTACHMENT C Page 2 The commission has provided guidance concerning the application of the standards for determining whether a significant hazards consideration exists by providing certain examples (51 FR 7751) of snendments that are considered not likely to involve significant hazards consideration.

Example (i) relates to "A purely administrative change to technical specifications:

for

example, a change to achieve consistency throughout the technical specifications, correction of an

error, or a

change in nomenclature".

The proposed change relates to this example in that the proposed changes are requested to achieve consistency throughout the technical specifications by providing clarification of the AFD surveillance requirements between 15%

and 50%

RTp and incorporating the STS reporting requirements for the steam generator tube inspection results.

Therefore, based on the above considerations, it is proposed to characterize the change as involving no significant hazards consideration.

i