ML20246M127: Difference between revisions

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j UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 May 11, 1989
NUCLEAR REGULATORY COMMISSION
                      /
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MEMORANDUM: David M. Verrelli, Chief Project Branch # 1 Division of Reactor Projects Region II THRU:               Elinor G. Adensam, Director Project Directorate II-1 Division of Reactor Projects I/II FROM:               John J. Hayes, Jr., Project Manager Project Directorate II-1 Division of Reactor Projects I/II
WASHINGTON, D. C. 20555
/
May 11, 1989 MEMORANDUM: David M. Verrelli, Chief Project Branch # 1 Division of Reactor Projects Region II THRU:
Elinor G. Adensam, Director Project Directorate II-1 Division of Reactor Projects I/II FROM:
John J. Hayes, Jr., Project Manager Project Directorate II-1 Division of Reactor Projects I/II


==SUBJECT:==
==SUBJECT:==
SOUTH CAROLINA ELECTRIC & GAS' COMMENTS ON V. C. SUMMER NUCLEAR STATION, UNIT NO. 1 INTERIM SALP Your memorandum of April 28, 1989 requested input from Project Directorate II-I of NRR'on comments number 6 and 7 on the V. C. Sumer interim SALP         l contained in the {{letter dated|date=April 24, 1989|text=April 24, 1989 letter}} from South Carolina Electric & Gas (SCE&G). Our response to these coments is as follows:                         1 Comment 6                                                                     l SCE&G's coment is appropriate and may be incorporated into the second sentence of the first paragraph on page 26 to read "Two examples of ..... developed by Westinghouse which established the tubesheet region tube alternate plugging (L ) criteria for steam generators at the Summer Station."
SOUTH CAROLINA ELECTRIC & GAS' COMMENTS ON V. C. SUMMER NUCLEAR STATION, UNIT NO. 1 INTERIM SALP Your memorandum of April 28, 1989 requested input from Project Directorate II-I of NRR'on comments number 6 and 7 on the V. C. Sumer interim SALP l
Comment 7 The interim SALP misstated the licensee's response to NRC Bulletin 88-08,       !
contained in the {{letter dated|date=April 24, 1989|text=April 24, 1989 letter}} from South Carolina Electric & Gas (SCE&G). Our response to these coments is as follows:
              " Thermal Stresses in Piping Connected to Reactor Coolant System". The         !
1 Comment 6 l
licensee's response did not require considerable NRC effort to obtain an acceptable program as stated in the interim SALP. The comment which was contained in the original drafts of the SALP was that the licensee's response was not timely. They had indicated at the October 6, 1988 meeting that they   '
SCE&G's coment is appropriate and may be incorporated into the second sentence of the first paragraph on page 26 to read "Two examples of..... developed by Westinghouse which established the tubesheet region tube alternate plugging (L ) criteria for steam generators at the Summer Station."
would submitted the additional infomation prior to restart. On October 6 restart was scheduled for December 1,1988. They did not provide the           ,
Comment 7 The interim SALP misstated the licensee's response to NRC Bulletin 88-08,
information until December 19, 1988 and restarted on December 28, 1988. The meeting sumary states that SCE&G would provide the additional information l                                                                           OFof Is 0905190051 890511 PDR   ADOCK 05000395 Q                   PDC L-_---__------
" Thermal Stresses in Piping Connected to Reactor Coolant System". The licensee's response did not require considerable NRC effort to obtain an acceptable program as stated in the interim SALP. The comment which was contained in the original drafts of the SALP was that the licensee's response was not timely. They had indicated at the October 6, 1988 meeting that they would submitted the additional infomation prior to restart. On October 6 restart was scheduled for December 1,1988. They did not provide the information until December 19, 1988 and restarted on December 28, 1988. The meeting sumary states that SCE&G would provide the additional information l
OFof Is 0905190051 890511 PDR ADOCK 05000395 Q
PDC L-_---__------


4, 4
4, 4
: l.                                                                         prior to restart._ Therefore, by the letter _of the law, the licensee met their commitment. Thus, the reference to Bulletin 88-08 should be deleted from paragraph one on page 27 and should read as shown in the Enclosure.
: l. prior to restart._ Therefore, by the letter _of the law, the licensee met their commitment. Thus, the reference to Bulletin 88-08 should be deleted from paragraph one on page 27 and should read as shown in the Enclosure.
Original Signed By:
Original Signed By:
John J. Hayes, Jr., Project Manager Project Directorate II-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation cc:             E. Adensam R. Prevatte DISTRIBUTION Centrab File NRC PDR Local PDR PDII-1 Reading.           ~
John J. Hayes, Jr., Project Manager Project Directorate II-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation cc:
S. Varga                             14-E-4 G. Lainas                           14-H-3 J. Hayes                             14-B-20 E. Jordan                           MNBB-3302 B. Grimes                           9-A-2 ACRS(10)                             P-315 Ildi         P )1 1
E. Adensam R. Prevatte DISTRIBUTION Centrab File NRC PDR Local PDR PDII-1 Reading.
                                .sw EKdensam 5/             89 5/{ /89 i
S. Varga
~
14-E-4 G. Lainas 14-H-3 J. Hayes 14-B-20 E. Jordan MNBB-3302 B. Grimes 9-A-2 ACRS(10)
P-315 Ildi P )1 1
.sw EKdensam 5/
89 5/{ /89 i


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27 performed.
27 performed.
The staff is concerned with the adequacy of the licensee's review of their contraccor's submittal when accident evaluations and radiological consequences are involved.
The staff is concerned with the adequacy of the licensee's review of their contraccor's submittal when accident evaluations and radiological consequences are involved.
He.           UJ%
He.
The licensee responses to NRC Bulletins and Generic Letters   were usually timely and complete. However, two exceptions"weasethe licentse's response to Bulletin 85-03, " Motor-Operated valve common mode failures during plant transients due to improper switch setting,",r d Bul h t!- SS-03 "'h:r,el Sta ,,,, .n ?;ging-Y's     C;nn u t;d t;
UJ%
                                          ".a ct r C = hnt Sy;t= " 'hnc submittal considerable NRC effort to obtain yacceptable program. t required
The licensee responses to NRC Bulletins and Generic Letters were usually timely and complete.
: 2.                                      A.#
However, two exceptions"weasethe licentse's response to Bulletin 85-03, " Motor-Operated valve common mode failures during plant transients due to improper switch setting,",r d Bul h t!- SS-03 "'h:r,el Sta,,,,
perform 6ne.e Rating Category: 2       Previous rating QA:   2   Licensing: 2
.n ?;ging-Y's C;nn u t;d t; ".a ct r C = hnt Sy;t= " 'hnc submittal considerable NRC effort to obtain acceptable program. t required y
: 3. Recommendations None V. Supp0RTING DATA A. Escalated Enforcement Action Severity Level III violation without civil penalty was issued on August 17, 1988, for failure of Operations staff to identify degraded service water flow from the RBCVs.     (395/88-13-01)
A.#
: 8. Management Conferences February 17, 1988     Vantage 5 fuel Amendment June 1, 1988           Inservice Testing Program August 17, 1988       Deletion of Fire Protection Technical Specifications August 31, 1988       Management meeting at NRC Headquarters to discuss short-term and long-term activities regarding resolution of motor operated valve and management problems.
2.
perform 6ne.e Rating Category: 2 Previous rating QA:
2 Licensing: 2 3.
Recommendations None V.
Supp0RTING DATA A.
Escalated Enforcement Action Severity Level III violation without civil penalty was issued on August 17, 1988, for failure of Operations staff to identify degraded service water flow from the RBCVs.
(395/88-13-01) 8.
Management Conferences February 17, 1988 Vantage 5 fuel Amendment June 1, 1988 Inservice Testing Program August 17, 1988 Deletion of Fire Protection Technical Specifications August 31, 1988 Management meeting at NRC Headquarters to discuss short-term and long-term activities regarding resolution of motor operated valve and management problems.
l October 6, 1988 NRC Bulletin 88-08 May 24, 1988 i
l October 6, 1988 NRC Bulletin 88-08 May 24, 1988 i
and   September 21,     1988 Containment Tendon Amendment.
and September 21, 1988 Containment Tendon Amendment.
October 13, 1988       Recurring deficiencies in fire protection.
October 13, 1988 Recurring deficiencies in fire protection.
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Latest revision as of 22:24, 1 December 2024

Submits Response to Util 890424 Comments on Interim Salp,Per 890428 Request.By Ltr of Law,Licensee Met Commitment.Thus, Ref to Bulletin 88-008 Should Be Deleted from Paragraph 1 on Page 27 & Should Read as Shown in Encl
ML20246M127
Person / Time
Site: Summer 
Issue date: 05/11/1989
From: Hayes J
Office of Nuclear Reactor Regulation
To: Verrelli D
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
IEB-88-008, IEB-88-8, NUDOCS 8905190051
Download: ML20246M127 (3)


Text

.

,.s

,, [(

g UNITED STATES g

NUCLEAR REGULATORY COMMISSION

, 7; j

WASHINGTON, D. C. 20555

/

May 11, 1989 MEMORANDUM: David M. Verrelli, Chief Project Branch # 1 Division of Reactor Projects Region II THRU:

Elinor G. Adensam, Director Project Directorate II-1 Division of Reactor Projects I/II FROM:

John J. Hayes, Jr., Project Manager Project Directorate II-1 Division of Reactor Projects I/II

SUBJECT:

SOUTH CAROLINA ELECTRIC & GAS' COMMENTS ON V. C. SUMMER NUCLEAR STATION, UNIT NO. 1 INTERIM SALP Your memorandum of April 28, 1989 requested input from Project Directorate II-I of NRR'on comments number 6 and 7 on the V. C. Sumer interim SALP l

contained in the April 24, 1989 letter from South Carolina Electric & Gas (SCE&G). Our response to these coments is as follows:

1 Comment 6 l

SCE&G's coment is appropriate and may be incorporated into the second sentence of the first paragraph on page 26 to read "Two examples of..... developed by Westinghouse which established the tubesheet region tube alternate plugging (L ) criteria for steam generators at the Summer Station."

Comment 7 The interim SALP misstated the licensee's response to NRC Bulletin 88-08,

" Thermal Stresses in Piping Connected to Reactor Coolant System". The licensee's response did not require considerable NRC effort to obtain an acceptable program as stated in the interim SALP. The comment which was contained in the original drafts of the SALP was that the licensee's response was not timely. They had indicated at the October 6, 1988 meeting that they would submitted the additional infomation prior to restart. On October 6 restart was scheduled for December 1,1988. They did not provide the information until December 19, 1988 and restarted on December 28, 1988. The meeting sumary states that SCE&G would provide the additional information l

OFof Is 0905190051 890511 PDR ADOCK 05000395 Q

PDC L-_---__------

4, 4

l. prior to restart._ Therefore, by the letter _of the law, the licensee met their commitment. Thus, the reference to Bulletin 88-08 should be deleted from paragraph one on page 27 and should read as shown in the Enclosure.

Original Signed By:

John J. Hayes, Jr., Project Manager Project Directorate II-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation cc:

E. Adensam R. Prevatte DISTRIBUTION Centrab File NRC PDR Local PDR PDII-1 Reading.

S. Varga

~

14-E-4 G. Lainas 14-H-3 J. Hayes 14-B-20 E. Jordan MNBB-3302 B. Grimes 9-A-2 ACRS(10)

P-315 Ildi P )1 1

.sw EKdensam 5/

89 5/{ /89 i

g.

(

27 performed.

The staff is concerned with the adequacy of the licensee's review of their contraccor's submittal when accident evaluations and radiological consequences are involved.

He.

UJ%

The licensee responses to NRC Bulletins and Generic Letters were usually timely and complete.

However, two exceptions"weasethe licentse's response to Bulletin 85-03, " Motor-Operated valve common mode failures during plant transients due to improper switch setting,",r d Bul h t!- SS-03 "'h:r,el Sta,,,,

.n ?;ging-Y's C;nn u t;d t; ".a ct r C = hnt Sy;t= " 'hnc submittal considerable NRC effort to obtain acceptable program. t required y

A.#

2.

perform 6ne.e Rating Category: 2 Previous rating QA:

2 Licensing: 2 3.

Recommendations None V.

Supp0RTING DATA A.

Escalated Enforcement Action Severity Level III violation without civil penalty was issued on August 17, 1988, for failure of Operations staff to identify degraded service water flow from the RBCVs.

(395/88-13-01) 8.

Management Conferences February 17, 1988 Vantage 5 fuel Amendment June 1, 1988 Inservice Testing Program August 17, 1988 Deletion of Fire Protection Technical Specifications August 31, 1988 Management meeting at NRC Headquarters to discuss short-term and long-term activities regarding resolution of motor operated valve and management problems.

l October 6, 1988 NRC Bulletin 88-08 May 24, 1988 i

and September 21, 1988 Containment Tendon Amendment.

October 13, 1988 Recurring deficiencies in fire protection.

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