ML20248M190

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Proposed Rev 2F to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves
ML20248M190
Person / Time
Site: Beaver Valley
Issue date: 05/19/1998
From:
DUQUESNE LIGHT CO.
To:
Shared Package
ML20248M189 List:
References
PROC-980519, NUDOCS 9806150126
Download: ML20248M190 (14)
v • d • e


Text

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I DUQUESNE LIGHT COMPANY Beaver Valley Power Station  ;

l Unit 2 I J

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.1 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES

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I PROPOSED REVISION 2F Pagesissued OSC Review Date g-17-9g WJ J f0/A- l W nager, System and Performance /84 - //df

.ngineering Departpegt Review Date g8j PKR-1 l kuoh, 6-A-%

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General Manager. i Vgg-8 Nuclear Operations Approval Date This " Proposed Revision" was made against Revisions 0, OA and OB of the present Unit 2 IST Program.

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980615o126 9eo609 PDR P

ADOCK 05000412 l PM

l Beaver Valley Power Station Unit a !ssue 2 Revis!on 0 l

INSERV!CE TESTING UST) PROGRAM FOR PUMPS AND VALVES Page 15 of 279 i

BVPS 2 IST I

! PUMP OUTLINE Pump  ; Pump l Code  ; System: 11 Safety injection

Name 21 A Low Head Safety! Number
2 SIS
  • P2 t A Class: 2 l i j injection Pump  !  !

' Function: Low pressure high volume safety injection. Type: Centnfugal l Dwg. OM No.: 11-1 i l Dwg. Coord.: E2 j Remarks: Pump is tested quarterly on recirculation flow and at full flow during refueling outages. Also see i PRR t, ame PRR2. 44,/ p&7 2F Parameter ! 20ST. Reg'd Comments l l (Frequency) l '

N NA NA Constant speed induction motor.

l AP 11.1 (O) X Calculated using Pump Discharge Pressure Indicator [2 SIS-Pl943]

(PRR2) and Pump Suction Pressure Indicator [2 SIS-Pl938], local. See PRR2  ;

for range and accuracy of Pump Suction Pressure Indicator l

[2 SIS Pl938).

11.14A (R) X Calculated using Pump Discharge Pressure Indicator [2 SIS-PIS43]

(PRR2) and Pump Suction Pressure indicator [2 SIS Pl938]. local. See PRR2 for range and accuracy of Pump Suction Pressure Indicator

[2 SIS P1938]. -

Q 11.1 (0) X Flow indicator [2 SIS-FIS970A], local.

11.14A (R) X Flow indicator [2 SIS-FIS45]. Control Room.

I V 11.1 (0) X Portable monitoring equipment using velocity units.

11.14A (R) X Portable monitoring equipment using velocity units. j l

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'l Beaver Valley Power Station Unit 2 Issue 2 Revision C l lNSERVICE TESTING (tST) PROGRAM FOR PUMPS AND VALVES Page 15 of 279 i BVPS 21ST '

{ PUMP OUTLINE l

' Pump iPump Code System: 11-Safety injection l' Name: 21B Low Head Saletyi Number: 2 SIS

  • P21 B Class: 2 injection Pump i j i

Function: Low pressure high volume safety injection. Type: Cenitifugal Dwg. OM No.: 11-1 i I Dwg. Coord.: G-2 l

! Remarks: Pump is tested quarterly on recirculanon flow and at full flow during refueling outages. Also see l l PRRigPRR2ano/ Ffg7  ;

2F i Parameter 2OST. Req'd Comments I (Frequency) l -N NA NA Constant speed induction motor.

AP 11.2 (0) X Calculated using Pump Discharge Pressure Indicator [2 SIS Pl944]

(PRR2) and Pump Suction Pressure Indicator [2 SIS P1939], local See PRR2 for range and accuracy of Pump Suction Pressure indicator

[2 SIS-Pl939].

I 11.14A (R) X Calculated using Pump Discharge Pressure Indicator [2GIS PIS44]

l (PRR2) and Pump Suction Pressure Indicator [2 SIS-PIS39], local. See PRR2 for range and accuracy of Pump Section Pressure Indicator *

[2 SIS-Pl939].

Q 11.2 (Q) X Flow indicator [2 SIS.FIS970B], local.

11.14A (R) X Flow indicator [2 SIS-Fl946], Control Room.

V 11.2 (0) X Portable monitoring equipment using velocity units.

l 11.14A (R) X Portable monitoring equipment using velocity units.

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BVPS-2 IST Prcgrcm Propmd Rsvizian 2F i

PUMP RELIEF REQUEST 7 I l

Pump Mark No(s): 2 SIS *P21A Code Class: 2 2 SIS *P21B System: 11 - Safety injection Function: To deliver low pressure high volume borated makeup water from the Refueling Water Storage Tank (RWST) to the Reactor Coolant System (RCS) during the injection phase following a large break loss of coolant accident (LOCA).

Test Requirement: Per Generic Letter No. 89-04, " Guidance On Developing Acceptable Inservice Testing Programs," Position 9," Pump Testing Using Minimum-Flow Retum Lines With or Without Flow Measuring Devices," Question Group 48 Response states,"The staff would prefer a more comprehensive test performed at some reduced frequency rather than relying on the mini-flow test that is performed quarterly." i

Background:

In response to this position, BVPS-2 tests the Low Head Safety injection (LHSI) Pumps at full flow conditions during each refueling outage in accordance vit's surveillance procedure 20ST-11.14A (LHS! Full Flow  ;

Test). The test is performed in Mode 6 with the reactor vessel head and j upper internals removed, with the RCS in direct communication with the j reheling cavity, and with the refueling cavity partially flooded. The  ;

fCO Ning is a background of milestones associated with this relief request. l

. On September 20,1996, full flow testing of the LHSI Pumps was I successfully completed per 2OST-11.14A during the sixth refueling l outage.

. On December 16,1996, the extension of the sixth refueling outage was completed following repair both Residual Heat Removal Pumps, and Cycle 7 was begun.

  • On December 16,1997, BVPS-2 was shutdown to resolve single failure design vulnerabilities that had been identified in the Control Room Emergency Breathing Air Pressurization System. It was anticipated that the forced outag's would be of a brief duration.

However, due to the emergence of several other technical and requiatory issues, the forced outage was extended to its current duration.

. Throughout the extended outage, the Unit has been maintained in

- Mode 5, with the reactor vessel head fully tensioned. The duration of the extended outage, in conjunction with the currently projected balance of fuel cycle operation schedule, would cause several ASME Section XI test intervals that are required to be performed at a

" Refueling" frequency to be exceeded. BVPS-2 Technical Specification 1.21, Table 1.2, " Frequency Notations," defines "R" l (Refueling) as "at least once per 18 months."

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BVPS-2 IST Pr:gr:m Propsud R vi ion 2F i l

l PUMP RELIEF REQUEST 7 (Continued)

. On March 20,1998, the 18 month (refueling frequency) due date for 20ST-11.14A entered its grace period.

l . The originally scheduled start date for the seventh refueling outage (2R7) of April 17,1998, was extended to September 4,1998.

. On August 5,1998, the 25% grace period for 20ST-11.14A will expire.

L e Due to the current duration of the extended outage, and based on the Reactor Engineering Group's estimate of 146 (75 min.i.,ium to 173 maximum) effective full power days (EFPD) still remaining for Cycle 7, the presently scheduled start data for 2R7 is projected to be extended l beyond September 4,1998.

Basis for Relief: BVPS-2 presently tests the Low Head Safety injection Pumps (LHSI) each quarter at a measured recirculation flowrate of approximately one-third of the total flow (approximately 1500 gpm) in full compliance with the requirements of ASME XI OM-6, Paragraph 5.1, " Frequency of Inservice Tests." This includes measuring flowrate, differential pressure

and vibrations, and ensures that the ECCS Flow Analysis as required by l BVPS-2 Technical Specification 4.5.2.b.2 and the BVPS-2 IST Program is met. BVPS-2 also tests the LHSI Pumps at full flow conditions during each refueling outage in response to Position 9 of Generic Letter No. 89-
04. The full flow test is performed in Mode 6 with the reactor vessel head and upper internals removed, with the RCS in direct communication with the refueling cavity, and with the refueling cavity
partially flooded. As the LHSI Pump transfers approximately 4400 gpm

, of borated water from the RWST to the RCS (refueling cavity), a Residual Heat Removal Pump is aligned to retum approximately 2100 gpm of water from the refueling cavity to the RWST. With an overall

inventory increase of approximately 2300 gpm to the RCS, the test is

! performed with the refueling cavity partially flooded and the reactor vessel head removed providing sufficient volume necessary to accept l the full flow discharge capacity of the LHSI Pumps to facilitate collection j of ASME XI OM-6 data. The test cannot be safely performed in Mode 5 (with the reactor vessel head installed) because there would be l insufficient surge volume available in the Pressurizer to accept the full L flow discharge capacity of the LHSI Pumps for the duration of the testing required by ASME XI OM-6. It is estimated that the Pressurizer would fill in ! css than 3 minutes which is not enough time to throttle flow, allow it to stabilize for 2 minutes, then gather ASME XI OM-6 data.

The LHSI Pumps were last tested at full flow conditions during the sixth refueling outage on 9/20/96. Because BVPS-2 has been in an extended outage, the start date for the seventh refueling outage (2R7) has slipped from the Spring of 1998 to the Fall of 1998. NUREG-1482, " Guidelines for Inservice Testing at Nuclear Power Plants," Cection 3.1.3,

" Scheduling of Inservice Test," defines a reiueling frequency as at least once every refueling outage. However, BVPS-2 Technical Specification 1.21, Table 1.2, defines "R" (Refueling) as at least once per 18 mo lths.

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ENPS-2 IST Pr:gr m Pr: pend R:,vicion 2F l PUMP RELIEF REQUEST 7 -(Contiaued)

In accordance with BVPS-2 Technical Specification 4.0.5(e), nothing in j the ASME Boiler and Pressure Vessel Code she,; be construed to supersede the requirements of any Technical Specification. Therefore, the BVPS-2 Technical Specification frequency definition must be followed. Since BVPS-2 knows that it will not meet the test interval requirements of Technical Specifications because of the delay in the 4 start of 2R7, BVPS-2 would be forced to take the Unit from Mode 5 into Mode 6 and remove the reactor vessel head in order to test the LHSI Pumps during the current extended outage.

In accordance with 10 CFR 50.55a(a)(3)(ii), relief is requested on the basis that compliance with the speci.'ied test requirement in the current mode of operation (Mode 5), cannot ta safely accomplished. Further, establishing the proper plant configuration would require reactor vessel head and upper intemals removal, and would result in a hardship or unusual difficulty without a compensating increase in the level of quality and safety.

Alternate Test: Full flow test the LHS! Pumps in Mode 6 when the Unit is shutdown for its seventh refueling ouiage per 2OST-11.14A (LHSI Full Flow Test).

Because the Technical Specification refueling test interval cannot be met due to the extended outage, a test interval extension of no more than 7%

months in excess of the grace period will be applied. This is based on the need to operate for approximately 146 (75 minimum to 173 maximum) EFPD to complete Cycle 7 following startup from the current extended outage with an additional allotment of forced outage time should it occur. The LHSI Pumps will be tested at full flow conditions no later than March 20,1999.

References:

Generic Letter No. 89-04, Position 9, Question Group 48.

OM-6, Paragraph 5.1 NUREG-1482, Section 3.1.3.

BVPS-2 Technical Specification 1.21, Table 1.2.

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BVPS-2 IST Pr:grcm Propossd Rsvizion 2F l

I VALVE RELIEF REQUEST 3 Valve Ihrk No(s): 2 SIS *6 2 SIS *109 2 SIS *S46 2 SIS *7 2 SIS *128 2 SIS *548 2 SIS *107 2 SIS *129 2 SIS *550 2 SIS *108 2 SIS *545 2 SIS *552 Category: A/C Class: ' 1. 2 System: 11 - Safety injection )

l.

Function: These Low Head Safety injection (LHSI) check valves must open to provide borated makeup water from the Refueling Water Storage Tank

-(RWST) to the Reactor Coolant System (RCS) daring the injection phase ]

following a large break loss of coolant accident (LOCA).

L Test Requirement: Per OM-10, Paragraph 4.3.2.1, " Exercising Test Frequency," check valves shall be exercised nominally every 3 months.

Background:

. As discussed in Valve Refueling Outage Justification No's. 14,19,21,25 and 27, BVPS-2 tests the LHSI check valves in conjunction with full flow

testing of the LHSI Pumps during each refueling outage in accordance with surveillance procedure 20ST-11.14A (LHSI Full Flow Test). The test is performed in Mode 6 with the reactor vessel head and upper i L internals removed, with the RCS in direct communication with the i refueling cavity, and with the refueling cavity partially flooded. The following is a background of milestones associated with this relief request. 1 e On September 20,1996, the LHSI check valves were successfully full-stroke exercised in the open direction per 20ST-11.14A during the sixth refueling outage.

e On December 16,1996, the extension of the sixth refueling outage was completed following repair both Residual Heat Removal Pumps, and Cycle 7 was begun.

  • On December 16,1997, BVPS-2 was shutdown to resolve single failure design vulnerabilities that had been identified in the Control l

Room Emergency Breathing Air Pressurization System. It was anticipated that the forced outage would be of a brief duration.

.However, due to the emergence of several other technical and regulatory issues, the forced outage was extended to its current l

duration.

p L e Throughout the extended outage, the Unit has been maintained in Mode 5, with the reactor vessel head fully tensioned. The duration of the extended outage, in conjunction with the currently projected '

balance of fuel cycle operation schedule, would cause several ASME

__ Section XI test intervals that are required to be performed at a Refueling" frequency to be exceeded. BVPS-2 Technical Specification 1.21, Table 1.2, " Frequency Notations," defines "R" (Refueling) as."at least once per 18 months."

~

BVPS-2 IST Prcgr::m Proposed Rsvirdon 2F VALVE RELIEF REQUEST 3 (Continued)

. On March 20,1998, the 18 month (refueling frequency) due date for 20ST-11.14A entered its grace period.

. The originally scheduled start date for the seventh refueling outage (2R7) of April 17,1998, was extended to September 4,1998.

e On August 5,1998, the 25% grace period for 2OST-11.14A will expire.

. Due to the current duration of the extended outage, and based on the )

Reactor Engineering Group's estimate of 146 (75 minimum to 173 maximum) effective full power days (EFPD) still remaining for Cycle 7, the presently scheduled start date for 2R7 is projected to be extended beyond September 4,1998.

Basis for Relief: These check valves are normally closed during plant operation and their safety position is open for LHSI. During plant operation when the RCS is.

at normal operating pressure, full-stroke exercising in the open direction by initiating the maximum required accident condition flowrate in accordance with Generic Letter No. 89-04, Position 1., in addition to part-stroke exercising in the open direction, cannot be performed because 4 the LHSI Pumps will not develop enough head to overcome RCS -

pressure. As stated in the Valve Refueling Outage Justifications; during cold shutdowns, full or part-stroke exercising in the open direction cannot j be performed because flow testing would require injection to the RCS  !

!- where there is not sufficient volume to receive the additional inventory. {

OM-10, Paragraph 4.3.2.2(e) states, "If exercising is not practicable )

cluring plant operation or cold shutdowns, it may be limited to full-stroke exercising during refueling outage."

Because the LHSI Pumps must be operated at full flow conditions in order to full stroke exercise these check valves, the Unit must be in Mode 6 with the reactor vessel head and upper intemals removed, with I the RCS in direct communication with the refueling cavity, and with the j refueling cavity partially flooded. As the LHSI Pump transfers j approximately 4400 gpm of borated water from the RWST to the RCS l l (refueling cavity), a Residual Heat Removal Pump is aligned to retum approximately 2100 gpm of water from the refueling cavity to the RWST.

With an overall inventory increase of approximately 2300 gpm to the RCS, the test is performed with the refueling cavity partially flooded and

l. the reactor vessel head removed providing sufficient volume necessary to accept the full flow discharge capacity of the LHSI Pumps. The test l- cannot be safely performed in Mode 5 (with the reactor vessel head installed) because there would be insufficient surge volume available in the Pressurizer to accept the full flow discharge capacity of the LHSI l Pumps.

The LHSI Pumps and check valves were last tested at full flow unditions during the sixth refueling outage on 9/20/96. Because BVPS-

! 2 has been in an extended outage, the start date for the seventh

{

i m

.s ....

. . BVPS-2 IST Program Proposed Ravicion 2F

. VALVE RELIEF REQUEST 3 (Continued) refueling outage (2R7) has slipped from the Spring of 1998 to the Fall of 1998. NUREG-1482, " Guidelines for inservice Testing at Nuclear Power Plants," Section 3.1.3, " Scheduling of Inservice Test," defines a refueling frequency as at least once every refueling outage. However, BVPS-2 1 L Technical Specification 1.21, Table 1.2, defines "R" (refueling) as at least '

once per 18 months. In accordance with BVPS-2 Technical Specification 4.0.5(e), nothing in the ASME Boi;er and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification. Therefore, the BVPS-2 Technical Specification frequency definition must be followed. Since BVPS-2 knows that it will not meet the test interval requirements of Technical Specifications because of the delay in the start of 2R7, BVPS-2 would be forced to take the Unit from Mode 5 into Mode 6 and remove the reactor vessel head in order to test the LHSI Pumps and check valves during the current extended outage.

In accordance with 10 CFR 50.55a(a)(3)(ii), relief is requested on the basis that compliance with the specified test requirement in the current mode of operation -(Mode 5), cannot be safely accomplished. Further, establishing the proper plant configuration would require reactor vessel head and upper intemals removal, and would result in a hardship or unusual difficulty without a compensating increase in the level of quality and safety.

Alternate Test: Full-stroke exercise the LHSI check valves in Mode 6 when the Unit is shutdown for its seventh refueling outage per 2OST-11.14A (LHSI Full FlowTest). Because the Tecnnical Specification refueling test interval cannot be met due to ths extended outage, a test interval extensic.1 of

. no more than 7% months in excess of the grace period will be applied.

This is based on the need to operate for approximately 146 (75 minimum to 173 maximum) EFPD to complete Cycle 7 following startup from the l current extended outage with an additional allotment of forced outage time should it occur. The LHSi check valves will be full stroke exercised no later than March 20,1999.

References:

OM-10, Paragraphs 4.3.2.1 and 4.3.2.2(e).

Generic Letter No. 89-04, Position 1.

' BVPS-2 Technical Specification 1.21, Table 1.2 1

i. J

}:.

.

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