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BVPS-2 Initial Stnrt-up Tzst
BVPS-2 Initial Stnrt-up Tzst Deferral Report for First Refuelina
      - e -
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Deferral Report for First Refuelina FSAR Section                             Title
FSAR Section Title 1) 14.2.12.77.01 Fuel Handling Test (PO)
: 1)         14.2.12.77.01                     Fuel Handling Test   (PO)
(PO-2.66.01)
(PO-2.66.01)
PO-2.66.01,   " Fuel Handling Equipment Test", Retest 66-005,
PO-2.66.01,
                      " Testing       of the Rod Cluster Control (RCC) Change Fixture", cannot be performed prior to the First Refueling Outage. The original test deferral specified a completion date of prior to the First Refueling Outage assuming that a Mode 5 outage of sufficient length would have occurred prior to the first refueling allowing sufficient time to test the RCC Change Fixture. Since a Mode 5 outage of sufficient length has not occurred, the RCC Change Fixture cannot be tested until during the first refueling when we perform the tool checkouts prior to moving fuel. The RCC Change Fixture was not used during initial fuel load because there was no irradiated fuel present.                   The RCC Change Fixture will be tested prior to moving fuel, and completion of PO-2.66.01 will be prior to the end of the First Refueling Outage. There are no Technical           Specification     requirements for the fuel handling equipment affected and the untested equipment is not safety related.
" Fuel Handling Equipment Test", Retest 66-005,
: 2)         14.2.12.33.01                     Automatic Steam Generator (SOV-2.24C.01)                   Water Level Control Test (SOV)
" Testing of the Rod Cluster Control (RCC) Change Fixture", cannot be performed prior to the First Refueling Outage.
SOV-2.24C.01,     " Automatic Steam Generator Water Level Control Test",         cannot be completed prior to the First Refueling Outage due to unavailability of required plant conditions. Section VII.F of the procedure is required to demonstrate repeatability of the Feedwater and Steam Flow Transmitters at 30, 50, 75, and 1 bus reactor power during a plant start-up. A containment entry is required to make adjustments to the steam flow transmitters prior to a subsequent repeatability verification. The original test deferral specified a completion date of prio. to the First Refueling Outage assuming that a Mode 5 outage of sufficient length would have occurred prior to the first refueling allowing the adjustments to be made. Since a Mode 5 outage of sufficient length has not occurred to permit adjustments to be made, testing could not be performed during any plant start-ups following plant trips.           No plant start-ups are presently scheduled prior to the First Refueling Outage.               I&C determined that there are no problems with a steam flow / feed flow mismatch and recommended that plant operations continue until fine tuning adjustments and checks can be performed.                   The test will be performed during start-up following the First Refueling Outage, and is expected to be completed by August 31, 1989. This testing activity is not required to support any Technical Specification requirements.
The original test deferral specified a completion date of prior to the First Refueling Outage assuming that a
Technical           Specification requirements 2.2.1 and 3.3.1.1. are verified by other methods.
Mode 5 outage of sufficient length would have occurred prior to the first refueling allowing sufficient time to test the RCC Change Fixture.
8903310245 890320                                                     TL PDR       ADOCK 05000412     s P                   PNU     ?
Since a Mode 5 outage of sufficient length has not occurred, the RCC Change Fixture cannot be tested until during the first refueling when we perform the tool checkouts prior to moving fuel.
8, jg W-__-____         . - _ - _ _ _ _
The RCC Change Fixture was not used during initial fuel load because there was no irradiated fuel present.
The RCC Change Fixture will be tested prior to moving fuel, and completion of PO-2.66.01 will be prior to the end of the First Refueling Outage.
There are no Technical Specification requirements for the fuel handling equipment affected and the untested equipment is not safety related.
2) 14.2.12.33.01 Automatic Steam Generator (SOV-2.24C.01)
Water Level Control Test (SOV)
SOV-2.24C.01,
" Automatic Steam Generator Water Level Control Test",
cannot be completed prior to the First Refueling Outage due to unavailability of required plant conditions.
Section VII.F of the procedure is required to demonstrate repeatability of the Feedwater and Steam Flow Transmitters at 30, 50, 75, and 1 bus reactor power during a plant start-up.
A containment entry is required to make adjustments to the steam flow transmitters prior to a
subsequent repeatability verification.
The original test deferral specified a completion date of prio. to the First Refueling Outage assuming that a
Mode 5 outage of sufficient length would have occurred prior to the first refueling allowing the adjustments to be made.
Since a Mode 5 outage of sufficient length has not occurred to permit adjustments to be made, testing could not be performed during any plant start-ups following plant trips.
No plant start-ups are presently scheduled prior to the First Refueling Outage.
I&C determined that there are no problems with a
steam flow / feed flow mismatch and recommended that plant operations continue until fine tuning adjustments and checks can be performed.
The test will be performed during start-up following the First Refueling Outage, and is expected to be completed by August 31, 1989.
This testing activity is not required to support any Technical Specification requirements.
Technical Specification requirements 2.2.1 and 3.3.1.1.
are verified by other methods.
8903310245 890320 TL PDR ADOCK 05000412 8,jg s
P PNU
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Shippingport, PA 15077 0004 JOHN D $1EBER '
Shippingport, PA 15077 0004 JOHN D $1EBER '
Vce Presdent - Nuclear Group                                                                                                         14121 643-5256.
Vce Presdent - Nuclear Group 14121 643-5256.
March 20, 1989 U. S. Nuclear Regulatory Commission Attn: ' Document Control Desk Washington, DC                     20555
March 20, 1989 U.
S. Nuclear Regulatory Commission Attn: ' Document Control Desk Washington, DC 20555


==Reference:==
==Reference:==
Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 BVPS-2 Initial Start-up Test Deferral Report for First; Refueling Gentlemen:
Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 BVPS-2 Initial Start-up Test Deferral Report for First; Refueling Gentlemen:
Forwarded is a BVPS-2 Initial Start-up Test Deferral. Report for First- ' Refueling                 identifying changes to the Initial Test Program as described in Chapter 14 of the FSAR.                                         These changes are made in accordance with the provisions of 10 CFR 50.59 and reported to NRC in accordance' with 50.59(b) within one month of initiating changes per BVPS-2 Facility Operating License - Item 2.C.(3).
Forwarded is a
BVPS-2 Initial Start-up Test Deferral. Report for First- ' Refueling identifying changes to the Initial Test Program as described in Chapter 14 of the FSAR.
These changes are made in accordance with the provisions of 10 CFR 50.59 and reported to NRC in accordance' with 50.59(b) within one month of initiating changes per BVPS-2 Facility Operating License - Item 2.C.(3).
Very truly yours,
Very truly yours,
                                                                                                          'D
'D D. Sieber Vice President Nuclear Group Attachment cc:
                                                                                                . D. Sieber Vice President Nuclear Group Attachment cc:             Mr. J. Beall, Sr, Resident Inspector Mr. W. T. Russell, NRC Region I Administrator Mr.-P. Tam, Project Manager p
Mr. J.
: c.                        .
Beall, Sr, Resident Inspector Mr. W. T. Russell, NRC Region I Administrator Mr.-P. Tam, Project Manager p
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COUNTY OF BEAVER.                                                                                             -)
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                      .Duquesne. Light,                                       (2) he is . duly authorized to execute-and. file the foregoing Submittal on behalf of said company, and (3) the statements
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a Not'ary Public in'and for said-before-me, Commonwealth' and County, personally appeared'J..D. Sieber,.who being duly
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.Duquesne. Light, (2) he is. duly authorized to execute-and. file the foregoing Submittal on behalf of said company, and (3) the statements
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Nc*zialSeal Sheh M. Fa' tore, Notary Putic -
$Wngport Baro, Beaver County My Commesion Expires Oct 23,1989
_ Member, Pennsylvane A:;800aten of Nolanes
_ Member, Pennsylvane A:;800aten of Nolanes
                      .            .  ..        - - _ _ - _ _ _ _ _ _ - - _ _ _ _ _ _ _ . _ = _ - _ . - - _ _ _ _ _ _ _ . _ - _ _ .}}
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Latest revision as of 21:06, 1 December 2024

Initial Startup Test Deferral Rept for First Refueling
ML20247D905
Person / Time
Site: Beaver Valley
Issue date: 03/20/1989
From: Sieber J
DUQUESNE LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8903310245
Download: ML20247D905 (3)


Text

_ _ _ _ _ _ _ _ _ _

r

~

BVPS-2 Initial Stnrt-up Tzst Deferral Report for First Refuelina

- e -

FSAR Section Title 1) 14.2.12.77.01 Fuel Handling Test (PO)

(PO-2.66.01)

PO-2.66.01,

" Fuel Handling Equipment Test", Retest 66-005,

" Testing of the Rod Cluster Control (RCC) Change Fixture", cannot be performed prior to the First Refueling Outage.

The original test deferral specified a completion date of prior to the First Refueling Outage assuming that a

Mode 5 outage of sufficient length would have occurred prior to the first refueling allowing sufficient time to test the RCC Change Fixture.

Since a Mode 5 outage of sufficient length has not occurred, the RCC Change Fixture cannot be tested until during the first refueling when we perform the tool checkouts prior to moving fuel.

The RCC Change Fixture was not used during initial fuel load because there was no irradiated fuel present.

The RCC Change Fixture will be tested prior to moving fuel, and completion of PO-2.66.01 will be prior to the end of the First Refueling Outage.

There are no Technical Specification requirements for the fuel handling equipment affected and the untested equipment is not safety related.

2) 14.2.12.33.01 Automatic Steam Generator (SOV-2.24C.01)

Water Level Control Test (SOV)

SOV-2.24C.01,

" Automatic Steam Generator Water Level Control Test",

cannot be completed prior to the First Refueling Outage due to unavailability of required plant conditions.

Section VII.F of the procedure is required to demonstrate repeatability of the Feedwater and Steam Flow Transmitters at 30, 50, 75, and 1 bus reactor power during a plant start-up.

A containment entry is required to make adjustments to the steam flow transmitters prior to a

subsequent repeatability verification.

The original test deferral specified a completion date of prio. to the First Refueling Outage assuming that a

Mode 5 outage of sufficient length would have occurred prior to the first refueling allowing the adjustments to be made.

Since a Mode 5 outage of sufficient length has not occurred to permit adjustments to be made, testing could not be performed during any plant start-ups following plant trips.

No plant start-ups are presently scheduled prior to the First Refueling Outage.

I&C determined that there are no problems with a

steam flow / feed flow mismatch and recommended that plant operations continue until fine tuning adjustments and checks can be performed.

The test will be performed during start-up following the First Refueling Outage, and is expected to be completed by August 31, 1989.

This testing activity is not required to support any Technical Specification requirements.

Technical Specification requirements 2.2.1 and 3.3.1.1.

are verified by other methods.

8903310245 890320 TL PDR ADOCK 05000412 8,jg s

P PNU

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W-__-____

s

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J.L'/

ff.3 L

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Shippingport, PA 15077 0004 JOHN D $1EBER '

Vce Presdent - Nuclear Group 14121 643-5256.

March 20, 1989 U.

S. Nuclear Regulatory Commission Attn: ' Document Control Desk Washington, DC 20555

Reference:

Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 BVPS-2 Initial Start-up Test Deferral Report for First; Refueling Gentlemen:

Forwarded is a

BVPS-2 Initial Start-up Test Deferral. Report for First- ' Refueling identifying changes to the Initial Test Program as described in Chapter 14 of the FSAR.

These changes are made in accordance with the provisions of 10 CFR 50.59 and reported to NRC in accordance' with 50.59(b) within one month of initiating changes per BVPS-2 Facility Operating License - Item 2.C.(3).

Very truly yours,

'D D. Sieber Vice President Nuclear Group Attachment cc:

Mr. J.

Beall, Sr, Resident Inspector Mr. W. T. Russell, NRC Region I Administrator Mr.-P. Tam, Project Manager p

c.

[

. S-1 1. -

, M' -

I

. col @lONWEALTH OF PENNSYLVANIA)-

.)

SS:

COUNTY OF BEAVER.

-)

On this MM.

day of

/M

, 1989,

. //fiu/2 ///N(iffe-(#

a Not'ary Public in'and for said-before-me, Commonwealth' and County, personally appeared'J..D. Sieber,.who being duly

sworn, deposed, and said that (1). he is Vice President.of

.Duquesne. Light, (2) he is. duly authorized to execute-and. file the foregoing Submittal on behalf of said company, and (3) the statements

' set forth in -the Submittal are.true and correct to the best of his

. knowledge, information and belief.

1 m

O W

Nc*zialSeal Sheh M. Fa' tore, Notary Putic -

$Wngport Baro, Beaver County My Commesion Expires Oct 23,1989

_ Member, Pennsylvane A:;800aten of Nolanes

- - _ _ - _ _ _ _ _ _ - - _ _ _ _ _ _ _. _ = _ - _. - - _ _ _ _ _ _ _. _ - _ _.