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| number = ML19095A047
| number = ML19095A047
| issue date = 05/20/1977
| issue date = 05/20/1977
| title = 05/20/1977 Letter Amendment to the Operating License Tech Spec Change No. 54, to Clarify Amount of Control Rod Movement Allowed Before Frequent Axiel Power Distribution Monitoring Surveillance Is Required
| title = Letter Amendment to the Operating License Tech Spec Change No. 54, to Clarify Amount of Control Rod Movement Allowed Before Frequent Axiel Power Distribution Monitoring Surveillance Is Required
| author name = Stallings C
| author name = Stallings C
| author affiliation = Virginia Electric & Power Co (VEPCO)
| author affiliation = Virginia Electric & Power Co (VEPCO)
Line 15: Line 15:


=Text=
=Text=
{{#Wiki_filter:VIRGINIA ELECTRIC .A.ND         POWER                         COMPANY R10HMOND, Vnio1N1A.. 23261
{{#Wiki_filter:VIRGINIA ELECTRIC.A.ND POWER COMPANY R10HMOND, Vnio1N1A.. 23261  
                              /
/
May. 20,. 1977 .
May. 20,. 1977.
Mr. Edson G. Case, Acting Director .                                                                                Serial No. 208.
Mr. Edson G. Case, Acting Director.
Office of Nuclear React.or Regulation                                                                           , LQA/DWSj r: krb Attn: Mr. R. W. Reid, Chie1                                                                                         FR/JTR
Office of Nuclear React.or Regulation Attn:
* Operating Reactors Branch No. 4                                                                         *Docket Nos.' 5*0-280
Mr. R. W. Reid, Chie1
          *Divisi~n of Operating Reactors                                                                                                         50-281 U. S. Nuclear Regulatory c*ommission                                                                                 License Nos. DPR-32 Washi_ngton, D. C. 20555                                                                                                                           DPR-37
* Operating Reactors Branch No. 4  
*Divisi~n of Operating Reactors U. S. Nuclear Regulatory c*ommission Washi_ngton, D. C.
20555  


==Dear Mr *. Case:==
==Dear Mr *. Case:==
 
Serial No. 208.
                        .. AMENDMENT *ro 'THE .:.OPERATING *u CENSE ,,
, LQA/DWSj r: krb FR/JTR
: "TECHNICAL SPECIFICATION CHANGE NO~ :54
*Docket Nos.' 5*0-280 50-281 License Nos. DPR-32 DPR-37
                        . SURRY POWER STAT I ON UN IT: NOS; 1 & 2
.. AMENDMENT *ro 'THE.:.OPERATING *u CENSE,,
* Pursuant to 10 CFR 50.90,. the Virginia Electric and Power Company
: "TECHNICAL SPECIFICATION CHANGE NO~ :54  
. SURRY POWER STAT I ON UN IT: NOS; 1 & 2
* Pursuant to 10 CFR 50.90,. the Virginia Electric and Power Company  
.her6by req~ests an amendment to Operating iicenses DPR-32.and DPR-37 for' Surry Powet Station Unit Nos. 1 and 2.:* The amendment requested is a change to the Technical Specifications and has been des_ignated as Cha_nge No *. 54*.
.her6by req~ests an amendment to Operating iicenses DPR-32.and DPR-37 for' Surry Powet Station Unit Nos. 1 and 2.:* The amendment requested is a change to the Technical Specifications and has been des_ignated as Cha_nge No *. 54*.
* At the ~equest of Surry*s ln~pection and Enforcement Principal lnspectoi this change is -proposed in order to clarify the amount of con-
* At the ~equest of Surry*s ln~pection and Enforcement Principal lnspectoi this change is -proposed in order to clarify the amount of con-
_trol rod movement.allowed before frequent Ax,ial Power Distribution Moni-toring (APDM) Surveillance is required .. The current wording of technical speiification 3.12.B.2.b(2)(a) (ii) does n~t uniquely ideniify the amount of control rod bank movement allowed before frequent APDM Surveillance is required *. The revised wordi~g better describes the control rod deadband.
_trol rod movement.allowed before frequent Ax,ial Power Distribution Moni-toring (APDM) Surveillance is required.. The current wording of technical speiification 3.12.B.2.b(2)(a) (ii) does n~t uniquely ideniify the amount of control rod bank movement allowed before frequent APDM Surveillance is required *. The revised wordi~g better describes the control rod deadband.
This specification is based on the fact that control rod movement up to that allowed will not significantly perturb the equilibrium*axial power and xenon distributions* and, consequently, will not significantly cha_nge the heat flux hot channel factor, FQ(Z). If, above *a specified power level (PTHRESHOLD), greater control rod movement is necessary, the specifi-cation provides f~r and requires frequent APDM Surveillance to verify that the FQ(?) limits are met until equilibrium conditions.are.reestablished. This specification is consistent with all Westinghouse plants that use APDM Sur-                                                                     0 ve i 11 ance.                                         .                          ~?~~*r.......""'                                                       .
This specification is based on the fact that control rod movement up to that allowed will not significantly perturb the equilibrium*axial power and xenon distributions* and, consequently, will not significantly cha_nge the heat flux hot channel factor, FQ(Z).
                                                            . .. '<?j.,:.V:~.*
If, above *a specified power level (PTHRESHOLD), greater control rod movement is necessary, the specifi-cation provides f~r and requires frequent APDM Surveillance to verify that the FQ(?) limits are met until equilibrium conditions.are.reestablished.
                                                                    ' ~-                        ,-,.
This specification is consistent with all Westinghouse plants that use 0 APDM Sur-ve i 11 ance.  
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Mr. Edson G. Cas~                  Sheet No. Z
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* These ctianges** have been reviewed by both Stat ion and System Nuclear I
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I Safety and Operating Corrrnittees. further, it has been determined.that these
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  /                          changes do* not involve an unreviewed safety question as defined in 10 CFR
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./
Mr. Edson G. Cas~
Sheet No. Z
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I                        . so.59.
* These ctianges** have been reviewed by both Stat ion and System Nuclear Safety and Operating Corrrnittees.
Very truly yours,
further, it has been determined.that these changes do* not involve an unreviewed safety question as defined in 10 CFR
                                                                                  ~ )/Ji;. J'";?~
. so.59.
                                    *.. *- .
cc:. Mr. Norman C. Moseley
* C.*M. Stallings Vice President-Power Supply and Production Operations cc:. Mr. Norman C. Moseley
\\
                                                            \}}
Very truly yours,  
~ )/Ji;. J'";?~
* C.*M. Stallings Vice President-Power Supply and Production Operations}}

Latest revision as of 03:47, 5 January 2025

Letter Amendment to the Operating License Tech Spec Change No. 54, to Clarify Amount of Control Rod Movement Allowed Before Frequent Axiel Power Distribution Monitoring Surveillance Is Required
ML19095A047
Person / Time
Site: Surry  Dominion icon.png
Issue date: 05/20/1977
From: Stallings C
Virginia Electric & Power Co (VEPCO)
To: Case E, Reid R
Office of Nuclear Reactor Regulation
References
Download: ML19095A047 (2)
v • d • e


Text

VIRGINIA ELECTRIC.A.ND POWER COMPANY R10HMOND, Vnio1N1A.. 23261

/

May. 20,. 1977.

Mr. Edson G. Case, Acting Director.

Office of Nuclear React.or Regulation Attn:

Mr. R. W. Reid, Chie1

  • Operating Reactors Branch No. 4
  • Divisi~n of Operating Reactors U. S. Nuclear Regulatory c*ommission Washi_ngton, D. C.

20555

Dear Mr *. Case:

Serial No. 208.

, LQA/DWSj r: krb FR/JTR

  • Docket Nos.' 5*0-280 50-281 License Nos. DPR-32 DPR-37

.. AMENDMENT *ro 'THE.:.OPERATING *u CENSE,,

"TECHNICAL SPECIFICATION CHANGE NO~ :54

. SURRY POWER STAT I ON UN IT: NOS; 1 & 2

.her6by req~ests an amendment to Operating iicenses DPR-32.and DPR-37 for' Surry Powet Station Unit Nos. 1 and 2.:* The amendment requested is a change to the Technical Specifications and has been des_ignated as Cha_nge No *. 54*.

  • At the ~equest of Surry*s ln~pection and Enforcement Principal lnspectoi this change is -proposed in order to clarify the amount of con-

_trol rod movement.allowed before frequent Ax,ial Power Distribution Moni-toring (APDM) Surveillance is required.. The current wording of technical speiification 3.12.B.2.b(2)(a) (ii) does n~t uniquely ideniify the amount of control rod bank movement allowed before frequent APDM Surveillance is required *. The revised wordi~g better describes the control rod deadband.

This specification is based on the fact that control rod movement up to that allowed will not significantly perturb the equilibrium*axial power and xenon distributions* and, consequently, will not significantly cha_nge the heat flux hot channel factor, FQ(Z).

If, above *a specified power level (PTHRESHOLD), greater control rod movement is necessary, the specifi-cation provides f~r and requires frequent APDM Surveillance to verify that the FQ(?) limits are met until equilibrium conditions.are.reestablished.

This specification is consistent with all Westinghouse plants that use 0 APDM Sur-ve i 11 ance.

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Mr. Edson G. Cas~

Sheet No. Z

  • .7" I

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  • These ctianges** have been reviewed by both Stat ion and System Nuclear Safety and Operating Corrrnittees.

further, it has been determined.that these changes do* not involve an unreviewed safety question as defined in 10 CFR

. so.59.

cc:. Mr. Norman C. Moseley

\\

Very truly yours,

~ )/Ji;. J'";?~

  • C.*M. Stallings Vice President-Power Supply and Production Operations
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