ML19276D978

Responds to NRC 781212 Ltr Re Violations Noted in IE Insp Rept 50-271/78-25.Corrective Actions:Malfunctioning Valve Repaired in Sodium Hypochlorite Injection Sys,Ph Problem Requires No Action

ML19276D978
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	01/04/1979
From:	Moody D VERMONT YANKEE NUCLEAR POWER CORP.
To:	Galen Smith NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19276D975	List: ML19276D978
References
NUDOCS 7903020054
Download: ML19276D978 (2)

Text

( VERhiONT YAN KEE NUCLEAR POWER CORPORATION SEVENTY SEVEN GROVE STREET

• 1 RUTLAND, VERMONT 05701 *

• REPLY TO

• ENGINEERING OFFICE TURNPIKE RO AD WESTBORO. M ASS ACHUSETTS 01581 TELEPHONE 617 366-9011 WY 79-3 January 4, 1979 United States Nuclear Regulatory Comission Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 Attention: Office of Inspection and Enforcement Mr. George H. Smith, Chief Fuel Facility and Materials Safety Branch

Reference:

(a) License No. DPR-28 (Docket No. 50-271)

(b) USNRC Letter to VYNPC, dated December 12, 1978 (Inspection Report 50-271/78-25)

Subject:

Response to I&E Inspection Report No. 78-25 This letter is written in response to Reference (b) which indicates that certain of our activities were not conducted in full compliance with Nuclear Regulatory Comission requirements. These alleged deficiencies were noted during an inspection conducted on Nove=ber 13-16, 1978, at the Vermont Yankee Nuclear Power Station in Vernon, Vermont. Information is submitted as follows in answer to the alleged deficiencies contained in the enclosure to your letter.

Item A - Section 1.B.2 of the Nonradiological Technical Specifications (NRTS) requires, in part, that the total residual chlorine concentration at the aerating structure be limited to 0.5 mg/1.

Contrary to this requirement, on October 20, 1978, the total residual chlorine concentration at the aerating structure was 4 1.1 mg/1.

e O Response- As discussed in the inspection report, this incident was the M result of a malfunctioning valve in the sodium hypochlorite C injection system. The corrective action described in the M report has bs.en taken and the valve was repaired. Since U this is an isolated incident of equipment failure, no further h7 action is determined necessarj.

Item B - Section 1.B. 3 of the NRTS requires that the hydrogen ion con-centration (pH) of plant discharges shall be controlled within pH limits of 6.5 - 8.5 except when due to natural causes.

i -

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United States Nuclear Regulatory Commission January 4, 1979 Attention: Office of Inspection and Enforcement Page 2 Contrary to this requirement, on April 29, 1978, the plant discharge pH was 8.8, while the river maximum pH during this day was 7.4.

Response- This item was discovered by the inspector during a review of chart recordings. Investigation of the Plant Chemistry Log, the Shift Supervisor Log, the Control Room Log, and the Makeup Demineralizer System Log could not provide any additional evidence to support this deviation from Technical Specifications. The PH monitor setpoints were also subsequently checked and verified correct. This item was determined as an unexplained isolated incident and no further action is determined necessary.

We trust this information will be satisfactory. Should additional information be required, please feel free to contact us.

Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION UK D. E. Moody (

Manager of Operations DCGlem