ML20247B181

Forwards Revised Pressure Temp Limits Rept for Byron,Unit 2. Reupdates Cover Page of P/T Limits Rept Document Along W/Figure 2.1,Figure 2.2 & Corresponding Table 2.1

ML20247B181
Person / Time
Site:	Byron
Issue date:	04/29/1998
From:	Graesser K COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20247B188	List: ML20247B181 ML20247B199
References
BYRON-98-0138, BYRON-98-138, NUDOCS 9805070307
Download: ML20247B181 (2)

Text

,

, Commonwealth likson Compan)

Hyrun Generating St.ition 4150 North German Churt h Itoad H) ron.11. 61010 9794 l Tel MI 6B M ii1

. )

April 29,199 1 TR: BYRON-98-0138 FILE: 2.01.0700 l

l U.S. Nuclear Regulatory Commission ,

Washington, D.C. 20555 l Attention: Document Control Desk

Subject:

Revision to Byron Unit 2 Pressure-Temperature Limits Report (PTLR)

Document Byron Nuclear Power Station, Unit 2 Facility Operatinglicense NPF-66 NRC Dockc. No. 50-455

References:

1. Byron Technical Specification Section 6.9.1.10,"RCS Pressure and Temperature IJmits Report."  ;

2. " Byron Station Units 1 and 2, and Braidwood Station Units 1 and 2, Acceptance for Referencing of Pressure Temperature ljmits Report (TAC NOS. h!98799, A198800, h198801, A198802)," NRC Safety Evaluation Report, R. A. Capra (NRR) to O. D. Kingsley (Comed),

datedJanuary 21,1998.

3. " Exemption from Requirements of 10 CFR 50.60 - Byron, Units 1 and 2, anc 3raidwood, Units 1 and 2 (FAC NOS. h198344, A198345, Af983c6, h198347)," NRC Safety Evaluation Report, G. F. Dick to O. D.

Kingsley, dated January 16,1998. /

This letter transmits a revision to the Byron Unit 2 Pressure Temperature Limits Report (PTLR) to meet the requirements of Byron Technical Specification 6.9.1.10 (Reference 1).

This revision updates the cover page of the PTLR document along with Figure 2.1, Figure gh 2.2, and corresponding Table 2.1. Figure 2.1 and 2.2 are the heatup and cooldown limit curves in the PTLR. Table 2.1 provides the corresponding data for both curves. In Reference 2, the NRC granted acceptance of Comed's intent to relocate the pressure / temperature limits to the PTLR document. In addition, in Reference 3, the NRC granted relief from the requirements of 10CFR50.60 to allow for the use of the 1996 l Addenda to the AShiE code in the generation of the pressure / temperature limits. Note that as part of the review process for the PTLR, the NRC reviewed the specific data and curves that are contained in this revision.

9805070307 900429 PDR ADOCK 05000455 p PDR

.rj A l'nicom Company

llYRON-98-0138 April 29,1998 Page 2 This letter represents the ofhcial notification to the NRC to meet the reporting requirements contained iri the Technical Specifications. If there are any additional questions, please contact Mascia Lesniak, Nuclear Licensing Administrator, at (630)-663-6484.

Sincerely

..e

~

,oY K. L. Graesser Site Vice President Byron Nuclear Power Station KLG/I2/rp Attachment A: Byron Unit 2 PTLR Revision Dated March 24,1998 cc: Regional Administrator - RIII Byron Project Manager - NRR Senior Resident Inspector - Byron Office of Nuclear Safety - IDNS l

l (pS98byttn 980138 doc) j