ML20035E756
| ML20035E756 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 04/07/1993 |
| From: | Maine Yankee |
| To: | |
| Shared Package | |
| ML20035E751 | List: |
| References | |
| NUDOCS 9304190206 | |
| Download: ML20035E756 (6) | |
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Attachment B.'
t Description of the ProDosed Technical SDecification Chanaes I
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9304190206 930407 9
- . PDR. ADOCK 05000309 i-F.
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Description of the Proposed Technical Specificati.ons
'ITEMi
. TECHNICAL NO.
SPECIFICATION
' DESCRIPTION OF CHANGE REASON FOR CHANGE 1.
5.5.A.2 Changes to PORC composition:
(page 5.5-1)
- 1. Designation of the Vice Chairman To provide additional definition as to from PORC membership; the composition of PORC membership.
- 2. Corrections to the titles of:
- a. Manager, Operations Department
- b. Manager, Maintenance Department
- c. Manager, Technical Support Department
- d. Reactor Engineering Supervisor
- e. Radiation Protection Manager
- f. Nuclear Safety Section Head
- 3. Inclusion of the Manager, Planning and Scheduling and the Manager, Plant Engineering in the PORC composition.
2.
5.5.A.5 Changes to the PORC quorum requirements to To ensure that the quorum of PORC (page 5.5-1) reflect the increased membership of PORC continues to be a majority of the PORC membership.
3.
5.14.2 Incorporate three new NRC approved To include these methodologies in the (page 5.14-2) references into the listing of methodologies generation of core operating limits as used in generating core operating limits.
defined in the Core Operating Limits Report.
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5.14.3 Placement of Specification 5.I4.3 on a new Format change only.
(page 5.14-3) page.
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i Attachment C Proposed Technical Specification Chances i
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1 5.5 REVIEW AND AUDIT
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5.5.A PLANT OPERATION REVIEW COMMITTEE 1.
FUNCTION l
The Plant Operation Review Committee (PORC) shall function to l
advise the Plant Manager on all matters ' related to nuclear safety.
2.
COMPOSITION l
The Plant Operation Review Committee shall be composed of the:
I Chairman:
Plant Manager -
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Vice Chairman: Designated-from the members of PORC by the i
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Plant Manager
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Member: Manager, Operations Department-
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Member: Manager, Maintenance Department j
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Member: Manager, Technical Support Department t
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Member:
Reactor Engineering Supervisor l
Member: Chemistry Section Head j
Member:
Instrument and Control Section Head
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Member:
Radiation Protection Manager i
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Member: Nuclear Safety Section Head
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Member: Manager, Planning & Scheduling
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Member: Manager, Plant Engineering 3.
ALTERNATES All alternate members shall be appointed in writing by the PORC Chairman to serve on a temporary basis; however, no more j
than two alternates shall participate as voting members in
. PORC activities or count toward a PORC quorum at any one time.
4.
MEETING FREOUENCY The PORC shall meet at least once per calendar month and as l
convened by the PORC Chairman or Vice Chairman.
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000 RUM l
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A quorum of the PORC shall consist of a minimum of six people as follows:
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- a. The Chairman or Vice Chairman plus five members, or f
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- b. The Chairman and Vice Chairman plus four members.
6.
PORC SUBCOMMITTEES Subcommittees may be utilized by the PORC to perform investigations, procedure reviews or any. other review as commissioned in writing by the PORC, provided:
5.5-1
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l Tech. Spec. 2.2
- 1..
YAEC-1099P, " Maine Yankee Fuel Thermal Performance Evaluation Model", dated February,1976.
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4 2.
YAEC-1115, " Application of Yankee's Reactor Physics Methods to i
Maine Yankee", dated October, 1976.
l 3.
YAEC-1296P, "DNBR Limit Methodology and Application to the Maine i
Yankee Plant", dated January,1982.
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" Maine Yankee Fuel Thermal Performance Evaluation Model", dated February, 1976.
2.
YAEC-1101, " Maine Yankee Plant Analysis Model Using GEMINI-II",
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dated June, 1976.
i 3.
YAEC-1102, " Maine Yankee Core Thermal-Hydraulic Model Using l
l COBRA IIIC", dated June, 1976.
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4.
YAEC-1103, " Maine Yankee Core Analysis Model Using CHIC-KIN,"
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dated September, 1976.
Protection System Setpoint 5.
YAEC-Ill0,
" Maine Yankee Reactor Methodology", dated September, 1976.
I 6.
YAEC-1115, " Application of Yankee's Reactor Physics Methods to i
Maine Yankee", dated October, 1976.
7.
YAEC-1241,
" Thermal Hydraulic Analysis of PWR Fuel Element Transients Using the CHIC-KIN Code", dated March, 1981.
8.
YAEC-1296P, "DNBR Limit Methodology and Application to the Maine Yankee Plant", dated January,1982.
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9.
YAEC-1447, " Application of RETRAN02 Mod 02 to the Analysis of the MSLB Accident at MYAPC", dated September, 1984.
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10.
YAEC-1464, " Modified Method for CEA Ejection Analysis of Maine l
Yankee Plant", dated December,1984.
- j 11.
YAEC-1160, " Application of Yankee WREN-Based Generic PWR ECCS Evaluation Model to Maine Yankee", dated July,1978.
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12.
Letter from G. D. Whittier (MYAPC) to A. C. Thadani (USNRC),
l MN-86-141, dated November 10, 1986.
13.
Letter from G. D. Whittier (MYAPC) to Victor Nerses (USNRC),
MN-87-59, dated May 21, 1987.
14.
YAEC 1300P, "RELAP5YA: A Computer Program for Light Water Reactor System Thermal-Hydraulic Analysis", Volumes 1, 2, 3, j
i dated October 1982.
i 15.
YAEC 1363-A, "CASM03G Validation", Apr il,1988.
16.
YAEC 1659-A, " Simulate 3 Validation and Verification", September, 1988.
[ 17.
YAEC 1642P, " Maine Yankee RPS Setpoint Methodology Using Statistical
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Combination of Uncertainties", March,1988.
[ 18.
YAEC 1752, " STAR Methodology Application for PWR's - Control Rod
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Ejection, Main Steam Line Break", September, 1990.
[ 19.
YAEC-1249P (dated April 1981); YAEC-1265P (dated June 1981); Letter, j
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Vermont Yankee to USNRC, " Vermont Yankee LOCA Analysis Method
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FROSSTEY Fuel Performance Code" (FROSSTEY-2), dated December 16,
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1987; and Letter, USNRC to Vermont Yankee, " Safety Evaluation of
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FROSSTEY-2 Computer Code", dated September 24, 1992.
l 5.14-2
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[ 5.14.3 The core operating limits shall be determined so that all applicable
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limits (e.g. fuel thermal-mechanical limits, core thermal hydraulic
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limits, ECCS limits, nuclear limits such as shutdown margin, and
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transient and accident analysis limits) of the safety analysis are met.
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5.14-3 La\\93nm\\9338