ML20093L826: Difference between revisions

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{{#Wiki_filter:3 :
{{#Wiki_filter:3 VIROINIA ELECTRIC AND Powan COMPANY
VIROINIA ELECTRIC AND Powan COMPANY
. RIcnwoxn, VIRGINIA 202 G1
                                        . RIcnwoxn, VIRGINIA 202 G1
.' W. L. Srz n er
    .' W. L. Srz n er
- Vics Passannwr October 15, 1984 wuci.=in o,== mon.
    - Vics Passannwr wuci.=in o,== mon.                         October 15, 1984 Mr. Harold R. Denton, Director                               Serial No. 523 Office of Nuclear Reactor Regulation                         N0/JHL:acm
Mr. Harold R. Denton, Director Serial No. 523 Office of Nuclear Reactor Regulation N0/JHL:acm
          ' Attn: 'Mr. James R. Miller, Chief                           Docket Nos. 50-338 Operating Reactors Branch No. 3                                   50-339 Division of Licensing                               License Nos. NPF-4
' Attn:
        'U. S. Nuclear Regulatory Commission                                           NPF-7 Washington, D. C. 20555 Gentlemen:
'Mr. James R. Miller, Chief Docket Nos. 50-338 Operating Reactors Branch No. 3 50-339 Division of Licensing License Nos. NPF-4
'U. S. Nuclear Regulatory Commission NPF-7 Washington, D. C. 20555 Gentlemen:
VIRGINIA ELECTRIC AND DOWER COMPANY NORTH ANNA POWER STATION UNIT NOS. 1 AND 2 PROPOSED TECHNICAL SPECIFICATION CHANGES
VIRGINIA ELECTRIC AND DOWER COMPANY NORTH ANNA POWER STATION UNIT NOS. 1 AND 2 PROPOSED TECHNICAL SPECIFICATION CHANGES
          -Pursuant to 10 CFR 50.90, the Virginia Electric and Power Company requests an amendment in the form of_ changes to the Technical Specifications to Operating 1 Licenses NPF-4 and NPF-7, for. North Anna Unit Nos. I and 2.
-Pursuant to 10 CFR 50.90, the Virginia Electric and Power Company requests an amendment in the form of_ changes to the Technical Specifications to Operating 1 Licenses NPF-4 and NPF-7, for. North Anna Unit Nos. I and 2.
The proposed Technical Specification changes will revise the reactor trip system instrumentation trip setpoint for intermediate range, neutron flux from leg than or equal to 25% of rated thermal power to less than or equal to 4 x 10   amps. -In addition, the Bases for the intermediate range,- neutron flux trip must be revised.       These changes are necessary because changes in core loading patterns and control rod position effects neutron flux at the excore
The proposed Technical Specification changes will revise the reactor trip system instrumentation trip setpoint for intermediate range, neutron flux from leg than or equal to 25% of rated thermal power to less than or equal to 4 x 10 amps.
          -detectors.- It is not possible to calibrate the intermediato range detectors to'directly measure percent of rated thermal power.
-In addition, the Bases for the intermediate range,- neutron flux trip must be revised.
The proposed Technical Specification changes for North Anna Unit No. I are provided 'in l Attachment 1. The proposed Technical Specification changes for North Anna Unit No. 2 are provided 'in Attachment       2. A safety evaluation discussing the proposed Technical Specification changes is provided in Attachment 3.
These changes are necessary because changes in core loading patterns and control rod position effects neutron flux at the excore
This request has.been refiewed and approved by the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control Staff. It has been
-detectors.- It is not possible to calibrate the intermediato range detectors to'directly measure percent of rated thermal power.
          ' determined that this request does not involve an unreviewed safety question as defined in 10 CFR 50.59.
The proposed Technical Specification changes for North Anna Unit No. I are provided 'in l Attachment 1.
          ~ lt has been determined that these proposed changes do not pose a significant
The proposed Technical Specification changes for North Anna Unit No. 2 are provided 'in Attachment 2.
        ' hazards consideration as defined in the Federal Register, dated April 6, 1983, Example (vi) which partially states, "A change which either may result in some             g increase to the probability or consequences of a previously analyzed accident         hcp or may reduce in some way,a safety margin, but where the results of the change             h are clearly within all acceptance criteria with respect to the system or                 l\
A safety evaluation discussing the proposed Technical Specification changes is provided in.
component specified.in the Standard Review Plan".     The proposed changes have 8410190217 341015                                                 c eb p DR ADOCK 05000338
This request has.been refiewed and approved by the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control Staff.
                                                                                    -M' T
It has been
D PDR
' determined that this request does not involve an unreviewed safety question as defined in 10 CFR 50.59.
~ lt has been determined that these proposed changes do not pose a significant
' hazards consideration as defined in the Federal Register, dated April 6, 1983, Example (vi) which partially states, "A change which either may result in some g
increase to the probability or consequences of a previously analyzed accident hcph or may reduce in some way,a safety margin, but where the results of the change are clearly within all acceptance criteria with respect to the system or l\\
component specified.in the Standard Review Plan".
The proposed changes have 8410190217 341015 eb c
DR ADOCK 05000338 D
p
-M' T
PDR


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gg                    [ :hisORMIA ELacraic Awn Powra                             Harold R. Denton Courawr    to s
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                                > b'een' . reviewed Lwith
> b'een'. reviewed Lwith respect - to the accident analyses in the North Anna UFSAR and Enone are. effected.
                                                    ~      ~
The UFSAR. analyses are in accordance with the
respect - to the accident analyses in the North Anna UFSAR and Enone are . effected. The UFSAR . analyses are in accordance with the h'-
~
acceptance criteria of-. Standard Review Plan 7.2,                 therefore these changes do not-pose a significant hazards consideration.
~
                                . Wei have s reviewed th'is : request' ' in accordance with the criteria in 10 CFR g.'
acceptance criteria of-. Standard Review Plan 7.2, therefore these changes do h'-
170.12. A'' voucher l check in the amount of $150 is enclosed as an application
not-pose a significant hazards consideration.
                  ,              . fee.
. Wei have s reviewed th'is : request' ' in accordance with the criteria in 10 CFR 170.12.
        . -                                                                                          V y truly yours, i f
A'' voucher l check in the amount of $150 is enclosed as an application g.'
                                                                                                            .(.             s W. L. Stewart Attachments
. fee.
                                        .-l. . Proposed Technical Specification Changes - Unit 1 2.' Proposed Technical Specification Changes - Unit 2
V y truly yours, f
                                      ' 3. --Safety Evaluation
i
                                      - 4. Voucher Check for $150.
.(.
s W. L. Stewart Attachments
.-l.
. Proposed Technical Specification Changes - Unit 1 2.'
Proposed Technical Specification Changes - Unit 2
' 3.
--Safety Evaluation
- 4.
Voucher Check for $150.
cc: ' Mr. James P. O'Reilly.
cc: ' Mr. James P. O'Reilly.
Regional Administrator' Region II
Regional Administrator' Region II
                                            ' Mr. M."
' Mr.
W. Branch ~
M." W. Branch ~
NKt, kesident' Inspector North Anna Power Station Mr. Charles Price Department of. Health 109 Governor-Street Richmond, Virginia 23219 E     m 6
NKt, kesident' Inspector North Anna Power Station Mr. Charles Price Department of. Health 109 Governor-Street Richmond, Virginia 23219 E
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'C(MMONWEALTH OF VIRGINIA ).
            'C(MMONWEALTH OF VIRGINIA ) .
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                                        )
CITY OF RICHMOND
CITY OF RICHMOND         )
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The foregoing document was acknowledged before me, in and for. the City and Commonwealth _ aforesaid, today by   W. L.         Stewart who is Vice President -
The foregoing document was acknowledged before me, in and for. the City and Commonwealth _ aforesaid, today by W.
Nuclear Operations, of the Virginia Electric and Power Company. He is duly authorized to execute and file the foregoing document - in behalf of that Company, and the statements in the document are true to the best of his knowledge and belief.
L.
Acknowledged before me this /f        day of/J       2      ch                   19 27   .
Stewart who is Vice President Nuclear Operations, of the Virginia Electric and Power Company.
My Commission expires:   A - J- 6                   ,  19   P a' .
He is duly authorized to execute and file the foregoing document - in behalf of that Company, and the statements in the document are true to the best of his knowledge and belief.
Om <2 . 7h m - -
day of/J ch 19 27 2
Notary Public (SEAL) s/ col I_         _
Acknowledged before me this /f My Commission expires:
A - J-6 19 P a'.
Om <2. 7h m - -
Notary Public (SEAL) s/ col I_


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ATTACHMENT 1 i.
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                              . _ . _ . _ _ . _ _ . - . . _ . . . . . _ - , . . - _ _ . .}}
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Latest revision as of 10:11, 13 December 2024

Application for Amend to Licenses NPF-4 & NPF-7,revising Tech Specs Re Reactor Trip Sys Instrumentation Trip Setpoints.Fee Paid
ML20093L826
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 10/15/1984
From: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To: Harold Denton, John Miller
Office of Nuclear Reactor Regulation
Shared Package
ML20093L829 List:
References
523, NUDOCS 8410190217
Download: ML20093L826 (4)


Text

3 VIROINIA ELECTRIC AND Powan COMPANY

. RIcnwoxn, VIRGINIA 202 G1

.' W. L. Srz n er

- Vics Passannwr October 15, 1984 wuci.=in o,== mon.

Mr. Harold R. Denton, Director Serial No. 523 Office of Nuclear Reactor Regulation N0/JHL:acm

' Attn:

'Mr. James R. Miller, Chief Docket Nos. 50-338 Operating Reactors Branch No. 3 50-339 Division of Licensing License Nos. NPF-4

'U. S. Nuclear Regulatory Commission NPF-7 Washington, D. C. 20555 Gentlemen:

VIRGINIA ELECTRIC AND DOWER COMPANY NORTH ANNA POWER STATION UNIT NOS. 1 AND 2 PROPOSED TECHNICAL SPECIFICATION CHANGES

-Pursuant to 10 CFR 50.90, the Virginia Electric and Power Company requests an amendment in the form of_ changes to the Technical Specifications to Operating 1 Licenses NPF-4 and NPF-7, for. North Anna Unit Nos. I and 2.

The proposed Technical Specification changes will revise the reactor trip system instrumentation trip setpoint for intermediate range, neutron flux from leg than or equal to 25% of rated thermal power to less than or equal to 4 x 10 amps.

-In addition, the Bases for the intermediate range,- neutron flux trip must be revised.

These changes are necessary because changes in core loading patterns and control rod position effects neutron flux at the excore

-detectors.- It is not possible to calibrate the intermediato range detectors to'directly measure percent of rated thermal power.

The proposed Technical Specification changes for North Anna Unit No. I are provided 'in l Attachment 1.

The proposed Technical Specification changes for North Anna Unit No. 2 are provided 'in Attachment 2.

A safety evaluation discussing the proposed Technical Specification changes is provided in.

This request has.been refiewed and approved by the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control Staff.

It has been

' determined that this request does not involve an unreviewed safety question as defined in 10 CFR 50.59.

~ lt has been determined that these proposed changes do not pose a significant

' hazards consideration as defined in the Federal Register, dated April 6, 1983, Example (vi) which partially states, "A change which either may result in some g

increase to the probability or consequences of a previously analyzed accident hcph or may reduce in some way,a safety margin, but where the results of the change are clearly within all acceptance criteria with respect to the system or l\\

component specified.in the Standard Review Plan".

The proposed changes have 8410190217 341015 eb c

DR ADOCK 05000338 D

p

-M' T

PDR

y;;

ly 9

4

+

[ :hisORMIA ELacraic Awn Powra Courawr to Harold R. Denton gg s

  • t I

> b'een'. reviewed Lwith respect - to the accident analyses in the North Anna UFSAR and Enone are. effected.

The UFSAR. analyses are in accordance with the

~

~

acceptance criteria of-. Standard Review Plan 7.2, therefore these changes do h'-

not-pose a significant hazards consideration.

. Wei have s reviewed th'is : request' ' in accordance with the criteria in 10 CFR 170.12.

A voucher l check in the amount of $150 is enclosed as an application g.'

. fee.

V y truly yours, f

i

.(.

s W. L. Stewart Attachments

.-l.

. Proposed Technical Specification Changes - Unit 1 2.'

Proposed Technical Specification Changes - Unit 2

' 3.

--Safety Evaluation

- 4.

Voucher Check for $150.

cc: ' Mr. James P. O'Reilly.

Regional Administrator' Region II

' Mr.

M." W. Branch ~

NKt, kesident' Inspector North Anna Power Station Mr. Charles Price Department of. Health 109 Governor-Street Richmond, Virginia 23219 E

m 6

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6

- ~

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y F

1-

,cy,

-d-wwi 1ge9 y

r"+e*'N**T-'--*****"1-*T et' 9-

.r-t

'C(MMONWEALTH OF VIRGINIA ).

)

CITY OF RICHMOND

)

The foregoing document was acknowledged before me, in and for. the City and Commonwealth _ aforesaid, today by W.

L.

Stewart who is Vice President Nuclear Operations, of the Virginia Electric and Power Company.

He is duly authorized to execute and file the foregoing document - in behalf of that Company, and the statements in the document are true to the best of his knowledge and belief.

day of/J ch 19 27 2

Acknowledged before me this /f My Commission expires:

A - J-6 19 P a'.

Om <2. 7h m - -

Notary Public (SEAL) s/ col I_

I'I f.

.. +,

9 4

ATTACHMENT 1 i.

J 4-

- t e

. _. _. _ _. _ _. -.. _..... _ -,.. - _ _..