ML19095A047
| ML19095A047 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| 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) | |
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
- 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*.
- 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~
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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
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Very truly yours,
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- C.*M. Stallings Vice President-Power Supply and Production Operations