ML19332D010
| ML19332D010 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 11/16/1989 |
| From: | Hunger G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RTR-NUREG-0991, RTR-NUREG-991 NUDOCS 8911290295 | |
| Download: ML19332D010 (2) | |
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'PH1'.ADELPHIA ELECTRIC COMPANY v
NUCLEAR GROUP HEADQUARTERS
' 955-65 CHESTERBROOK BLVD.
WAYN E,' PA 19087 5691 November 16, 1989 m
Docket Nos.- 50-352 50-353 License Nos. NPF NPF-851 i
-1 U.S. Nuclear Regulatory Commission Attn:
Document Control Desk' LWashington, DC 20555
. SUBJECT.
Limerick Generating Station, Units 1 and-2 Safety Evaluation' Report - NUREG-0991 Comments on Supplement No. 9
' Gentlemen:
L
.On August'25,.1989,. Philadelphia Electric Company.(PECo) l-received.the full powcr operating license (NPF-85) for Limerick
. Generating Station-(LGS), Unit 2.
Also issued at that-time was Supplement No. 9 to the LGS Safety Evaluation Report (NUREG-0991).
PECo has reviewed Supplement No. 9 and has identified a few minor editorial ~and/or technical' items which we! consider to warrant
' documentation.
These items are discussed in the attachment'.
p
'If you have any questions regarding this matter, please L
contact us.
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Very truly yours, q
p G.A.-Hunger,f'Jr.
o l
Director Licensing Section
.gRl1290295 891116 E
Wl/0CK 05000353 PDC Attachment 0
0 cc:
W. T. Russell, Administrator, Region I, USNRC T. J.' Kenny, USNRC Senior Resident Inspector, LGS
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ATTACHMENT age L
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b Editorial and Technical Comments on Supplement No. ?
[
to NUREG 0991 t
- Editorial items are' identified below'in the format of'an. errata for
- Supplement'No.19 to.NUREG-0991.
Location:
Item.
Revisior.
4
.Page' 15-8Fline 17:
41.2 GPM 41.2 GPM per pump 0
fagef16-1, line 46:
60% F 60 F Page 16-2, line 30 106 107 y
LM
- Page 16-2,:line 31 109
'110 l
.Pagel16-2, line 31-flow-power N
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- Technical items are discussed individually below.
A.
Cht Fage 16-2, 'line 4, the initial parameters for licensing basis
[
transient analyses are identified =as 100 percent flow, 100:
percent power for. pressurization transients.
However, these parameters were identified as 100 percent-flow, 104.3 percent.
power:throughout the Extended Load Line Limit Analysis (ELLLA)
~
forlDGS, Unit 2, Cycle'1 (
Reference:
NEDC-31577P).. Refer to t
NEDC-31577P. Sections 1,
- 3. 2, -
3.3.2, 3.4, and Tables 3-1, 3-3, and'3-4:for examples.
'2his concern also exists in the original Unit =2 ELLLA approval =(dated = June 14, 1989), and in the safety evaluations'for the Unit 1-Technical Specifications Amendment
- Nos. 7'(dated August 14, 1987)'and 19 (dated April 24,x1989).
B..
On Page 16-2, the first paragraph indicates that the transient analyses for the-ELLLA extension demonstrate that the licensing basis results bound the ELLLA region results for all minimum 4
- critical ~ power. ratio events and:that no Technical Specifications
- changes are required.
However, NEDC-31577P identified two ELLLA
' region transient analyses,: Load Rejection with-Bypass Failure and lFeedwater Controller Failure, wherecthe resultr are more limiting
-with respect to the minimum critical power rat 2o (MCPR) than corresponding analyses at the licensing basis point.
Of these, only,the Feedwater Controller Failure without turbine bypass i
,(FWCF-w/o BP) is more limiting for.tne MCPR than the general
' licensing bases which would have been reflected in the Technical Specifications if the ELLLA had not been done.
Refer to NEDC-31577P Sections 1, 3.3.1.1, 3.4 and Tables 3-2 and 3-3.
The current Technical Specifications issued with the Unit 2 Operating L
License contain the limitations necessary to reflect the ELLLA and maintain the margin of safety.
(Refer to Technical Specifications Figure 3.2.3-la.) This concern also exists in the original Unit 2 ELLLA approval (dated June 14, 1989).
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