ML20059M984
| ML20059M984 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 11/10/1993 |
| From: | Hunger G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9311300037 | |
| Download: ML20059M984 (5) | |
Text
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PIIILADELPIIIA ELECTRIC COMPANY g
NUCLEAR GROUP llEADQUARTERS 955-65 CHESTERBROOK BLVD.
WAYNE, PA 19087-5691 (215) MO-WX)
STADON SUPPORT DEPARTMENT November 10,1993 Docket No. 50-353 Ucense No. NPF-85 US Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Umerick Generating Station, Unit 2 Technical Specifications Change Request No. 93-14-2 Additional Information Gentlemen:
By letter datec August 27,1993, Philadelphia Electric Company (PECo) submitted a one time (i.e., temporary) Umerick Generation Station (LGS), Unit 2, Technical Specifications (TS) Change Request (i.e., No. 93-14-2) that proposed to extend the allowed outage time (AOT) for the Unit 2 Residual Heat Removal Service Water
-(RHRSW) system as well as the Suppression Pool Spray and Suppression Pool Cooling -
modes of the Residual Heat Removal (RHR) system to 288 hours0.00333 days <br />0.08 hours <br />4.761905e-4 weeks <br />1.09584e-4 months <br /> (i.e., twelve days) on-two separate occasions during the fifth Unit 1 Refueling Outage. As a result of a phone conversation on October 22,1993 between F. Rinaldi of the NRC, and R. M. Krich, PECo Ucensing Manager, the attached information was requested and is being submitted by-
- this letter.
9311300037.931116 '
.PDR ADDCK 05000353 P.
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, Lim rick G:nerating Station, Unit 2 Pag 3 2 Technical Specifications Change Request
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No. 93-14-2 Additional Information This additional information is being submitted under affirmation, and the associated affidavit is enclosed. If you have any questions or need additional information, please contact us.
Very truly yours,
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o G. A. Hunger, Director Licensing Section Enclosure Attachment cc:
T. T. Martin, Administrator, Region I, USNRC (w/ enclosure, attachment)
N. S. Perry, USNRC Senior Resident inspector, LGS (w/ enclosure, attachment)
W. P. Dornsife, Director, PA Bureau of Radiation Protection (w/ enclosure, attachment)
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hi-COMMONWEALTH OF PENNSYLVANIA:
ss.
COUNTY OF CHESTER D. R. Helwig, being first duly sworn, deposes and says:
That he is Vice President of Philadelphia Electric Company; that he has read the foregoing Additional Information concerning the Technical Specifications Change Request No. 93-14-2 affecting operation of Limerick Generation Station, Unit 2, to facilitate a -
change to the Limerick Generating Station Residual Heat Removal Service Water System, and knows the contents thereof; and that the statements and matters set forth therein are true and correct to the best of his knowledge, information, and belief.
s Vice President Subscribed and sworn to before me this /o day of M +om/ i.1993.
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ATTACHMENT l
Umerick Generating Station, Unit 2 Technical Specifications Change Request No. 93-14-2, dated August 27,1993 Additional Information REQUESTED INFORMATION is there any training or operational guidance, in place or required, to aid plant operators during a Unit 2 Loss of Coolant Accident (LOCA) if it were to occur during the proposed extended allowed outage times (AOTs) while Umerick Generating Station (LGS)
Unit 1 and Unit 2 are in the opcrational configuration described in the Technical Specifications Change Request No. 93-14-27
RESPONSE
Operation with one loop of Residual Heat Removal Service Water (RHRSW) inoperable is in accordance with the design basis of Limerick Generation Station (LGS).
1 Operations personnel are fully qualified by normal periodic training to respond to and mitigate a Design Basis Accident, including the actions needed to ensure decay heat removal while LGS Unit 1 and Unit 2 are in the operational configuration described in proposed Technical Specifications (TS) Change Request No. 93-14-2 submitted on August 27,1993.
Accordingly, procedures are already in place that cover safe plant shutdown and decay heat removal for situations applicable to those in the proposed i
AOTs. Decay heat removal once Unit 2 is in Operational Conditions (OPCONs) 3 (i.e.,
Hot Shutdown),4 (i.e., Cold Shutdown), and 5 (i.e., Refueling).will be provided by the Residual Heat Removal (RHR) System, the terraining operable RHR Heat exchanger, and the associated operable loop of RHRSW.
Two loops of shutdown cooling are required to be operable in OPCONS 3 and 4 in accordance with T9 Sections 3.4.9.1 and 3.4.9.2, or an alternate method of decay heat removal is required to be demonstrated. Since only one loop would be operable, alternate decay heat removal methods will be available such as establishing a shutdown cooling path through the Automatic Depressurization System (ADS) valves together with '
suppression pool cooling or using the main turbine condenser as a heat sink if offsite power is available. These methods will satisfy the shutdown cooling requirements while the reactor in in OPCONs 3 and 4. In OPCON 5, alternate decay heat removal methods such as Rea:: tor Water Cleanup (RWCU) system, can be utilized to satisfy the shutdown cooling reqt.irements after a sufficient time following plant shutdown. However, LGS personnel also recognize that the Unit 2 operational configuration during the proposed extended allowed outage times (AOTs) should be emphasized, and therefore a special procedure (SP) will be written in accordance with LGS Administrative Procedure A-23,
" Generation and Performance of Special Procedures, Modification AcceptanceTest (MAT),
and Plant Evolution / Special Test Procedures (PEST)."
Attachment Page 2 Furthermore, Procedure A-23 requires LGS personnel to include in the special procedure identification of the differences in the system line-ups, plant configuration, and operating j
procedures between the PEST procedures and normal operations. The procedure also requires steps to brief operations personnel. The SP will address the applicable existing shutdown and decay heat removal procedures associated with the operational configuration described in the August 27,1993 submittal.
The operations personnel qualifications, in conjunction with the SP and shift briefings, ensure that plant personnel are capable of responding to a Unit 2 Design Basis Accident while in the proposed operational configuration, and that plant personnel will be fully aware of this plant configuration during the proposed extended AOTs.
REQUESTED INFORMATION How will LGS personnel confirm the operability of those systems described in the TS Change Request No. 93-14-2 which are relied upon to mitigate the effects of a Unit 2 LOCA during the proposed extended AOTs?
RESPONSE
The systems relied upon to be operable in order to mitigate the effects of a LOCA, establish shutdown conditions and provide decay heat removal during the extended AOTs as described in TS Change Request No. 93-14-2, will be listed in the Prerequisites Section of the SP described above. These systems are the remaining loop of RHRSW, associated RHR loop and heat exchanger, Emergency Service Water, associated Emergency Diesel Generators, High Pressure Coolant injection, Core Spray and at least one alternate decay heat removal method system depending on OPCONS such as ADS or the main turbine condenser and RWCU. In addition, the SP will also require that these systems will be verified by operations personnel to be in compliance with respect to individual Technical Specificatiors Surveillance Requirements prior to entry into and during the proposed extended AOTs. Furthermore, any testing of these systems will be accomplished, to every extent possible, such that no testing will be performed during the time that the plant is in the condition permitted by the proposed extended ACTS.
O These procedural conditions will help ensure the systems required by TS Change Request No. 93-14-2 to be operable prior to entry into and during the extended AOTs are indeed operable.