ML20203E677: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot insert)
 
(StriderTol Bot change)
 
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:}}
{{#Wiki_filter:--
(                                                                        ENCLOSURE 1 -                                            i E                                                                    NOTICE OF VIOLATION                                            I L                                                                                                                                      l L                Connecticut Yankee Atomic Power Company-                                              Docket No.- 50 213          i i                Haddcm Neck Plant -                                                                    License No. DPR 61    '
l                                                                    .              _
l'                During NRC inspections conducted on October 12,1997 - January 12,1998, a violation of                              .
;              - NRC requirements was identified, in accordance with the "Genorr Statement of Policy and Procedure for NRC Enforcement Actions," (60 F.R. 34381; Jr,30,1995), the                                      ,
L                violation is listed below.                                                                                        l 1
                        - 10 CFR 50 Appendix B, Criterion ill, " Design Control," requires, in part, that                          ,
i                        measures be established to assure that applicable regulatory requirements and the                            '
design basis for structures, systems, and components are correctly translated into specifications, drawings, procedures, and instructions. These measures shall provide for verifying or checking the adequacy of design, such as by the                                    !
2 performance of design reviews, by the use of alternate or simplified calculational
]                        methods, or by the performance of a suitable testing pr~aram.
.                        UFSAR Section 9.4.2.2 states that the design flow rate of the spent fuel building                            l (SFB) exhaust fan exceeds the supply fan capacity to maintain a negative pressure
;                        in the spent fuel building. The design flow rates of the exhaust fan is 13,000 cfm, and 12,000 cfm for the supply fan, with an assumed 1000 cfm building inleakage.
                                                                                                                                      ]
Contrary to the above, the licensee did not provide for verifying or checking the                          >
                        -adequacy of design for the following systems and components:                                              j i                        The licensee determined on October 13,1997 that the SfB exhaust fan did l                        not meet its design flow of 13,000 cfm; further, it could not maintain the spent fuel building pressure negative wi^h the SFB supply fan running. The SFB exhaust fan was rendered incapable of providing the design flow as a result of plant modifications in 1974. Ventilation system changas made per plant design change requests 116,149 and 163 replaced the original primary auxiliary building fans' with new fans having a higher capacity. Licensee d
measures to verify the adequacy of the design through calculations or testing were not adequate to assure there was no adverse impact on the interfacing                              ,
SFB fans (LER 9718).
:                        This is a Severity Level IV violation (Supplement 1).
The NRC has concluded that the information regarding the reason for this violation, the
;                corrective actions taken and planned to correct the violation and prevent recurrence and the date when full compliance was achieved are already adequately addressed in -
Inspection Report 50-213/97-09. However, you are required to submit a written statement
,                or explanation pursuant to 10 CFR 2.201 if the description therein does not accurately 4
reflect your corrective actions or position. In that case, or if you choose to respond, clearly mark your response as a " Reply to a Notice of Violation," and send it to the U.S.
Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D.C. 20555 with a copy to the Regional Administrator, Region I, and a copy to the NRC Resident i
9902270105 900217 PDR- ADOCK 05000213 G                          pop
: .      -      _=          -  . - - - - _                  a  . - .        _-
                                                                                                    -..        ..  . .  -}}

Latest revision as of 21:37, 31 December 2020

Notice of Violation from Insp on 971012-980112.Violation Noted:Licensee Did Not Provide for Verifying or Checking Adequacy of Design for Listed Sys & Components
ML20203E677
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 02/17/1998
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20203E548 List:
References
50-213-97-09, 50-213-97-9, NUDOCS 9802270105
Download: ML20203E677 (2)


Text

--

( ENCLOSURE 1 - i E NOTICE OF VIOLATION I L l L Connecticut Yankee Atomic Power Company- Docket No.- 50 213 i i Haddcm Neck Plant - License No. DPR 61 '

l . _

l' During NRC inspections conducted on October 12,1997 - January 12,1998, a violation of .

- NRC requirements was identified, in accordance with the "Genorr Statement of Policy and Procedure for NRC Enforcement Actions," (60 F.R. 34381; Jr,30,1995), the ,

L violation is listed below. l 1

- 10 CFR 50 Appendix B, Criterion ill, " Design Control," requires, in part, that ,

i measures be established to assure that applicable regulatory requirements and the '

design basis for structures, systems, and components are correctly translated into specifications, drawings, procedures, and instructions. These measures shall provide for verifying or checking the adequacy of design, such as by the  !

2 performance of design reviews, by the use of alternate or simplified calculational

] methods, or by the performance of a suitable testing pr~aram.

. UFSAR Section 9.4.2.2 states that the design flow rate of the spent fuel building l (SFB) exhaust fan exceeds the supply fan capacity to maintain a negative pressure

in the spent fuel building. The design flow rates of the exhaust fan is 13,000 cfm, and 12,000 cfm for the supply fan, with an assumed 1000 cfm building inleakage.

]

Contrary to the above, the licensee did not provide for verifying or checking the >

-adequacy of design for the following systems and components: j i The licensee determined on October 13,1997 that the SfB exhaust fan did l not meet its design flow of 13,000 cfm; further, it could not maintain the spent fuel building pressure negative wi^h the SFB supply fan running. The SFB exhaust fan was rendered incapable of providing the design flow as a result of plant modifications in 1974. Ventilation system changas made per plant design change requests 116,149 and 163 replaced the original primary auxiliary building fans' with new fans having a higher capacity. Licensee d

measures to verify the adequacy of the design through calculations or testing were not adequate to assure there was no adverse impact on the interfacing ,

SFB fans (LER 9718).

This is a Severity Level IV violation (Supplement 1).

The NRC has concluded that the information regarding the reason for this violation, the

corrective actions taken and planned to correct the violation and prevent recurrence and the date when full compliance was achieved are already adequately addressed in -

Inspection Report 50-213/97-09. However, you are required to submit a written statement

, or explanation pursuant to 10 CFR 2.201 if the description therein does not accurately 4

reflect your corrective actions or position. In that case, or if you choose to respond, clearly mark your response as a " Reply to a Notice of Violation," and send it to the U.S.

Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D.C. 20555 with a copy to the Regional Administrator, Region I, and a copy to the NRC Resident i

9902270105 900217 PDR- ADOCK 05000213 G pop

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

-.. .. . . -