ML20247H145

Forwards 1988 Annual Decommission Rept 16

ML20247H145
Person / Time
Site:	Peach Bottom
Issue date:	05/22/1989
From:	Hunger G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8905310168
Download: ML20247H145 (2)

Text

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T.S. Appendix A, 8.2.4(a)

PHILADELPHIA ELECTRIC COMPANY 23O1 M ARKET STREET P.O. BOX 8699 PHILADELPHIA A. PA.19101 (215)841 4000 May 22, 1989 s Docket No. 50-171 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

Subject:

Peach Bottom Atomic Power Station Unit No. 1 1988 Annual Decommission Report No. 16

Dear Sir:

Attached is the 1988 Peach Bottom Atomic Power Station Unit No. 1 Decommission Report for the period January 1, 1988 through December 31, 1988. The report is submitted pursuant to reporting requirement 8.2.4.(a)in Appendix A to License No. DPR-12.

Very truly yours,

.0 fo G.A. Hunger, Jr.

Director Licensing Section Nuclear Support Division cc: W. T. Rtssell, Administrator, Region I, USNRC T. P. Johnson, USNRC Senior Resident Inspector P. B. Erickson, PB Unit 1 NRC Project Manager T. E. Magette, State of Maryland T. M. Gerusky, Commonwealth of Pennsylvania 8905310168 890522 (

PDR ADOCK 05000171 R PNU

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I M PHILADELPHIA ELECTRIC COMPANY Peach Bottom Atomic-Power Station Unit No. 1 1988 Annual Decommission Report Docket No. 50-171 The following summarizes the status of the. Peach Bottom Unit No. l' Decommission Facility for the year 1988, based on the semi-annual inspections performed in January and July, required by Technical Specification.8.2.4(a).

L . No significant damage or structural deterioration was observed in the security fence surrounding the exclusion area.

2. No significant damage or structural deterioration was observed in the containment vessel, spent fuel building enclosure, radwaste building or in the designated barricades within the exclusion area.

3.- There is no evidence of ground water movement between the exclusion area and outside the exclusion area.

4. There is no significant change in the radiation or contamination levels in the facility.

S. There are no removable contamination levels above 1000 1 dpm/100cm2.

6. Radiation levels in all areas do not exceed 0.2 mR/hr.

7. . Maximum airborne activity was 2.94 x 10-10 uCi/cc.

8. Radiation levels on the absolute filter sample on the containment equalization line do not excccd 0.1 mR/hr.

9. There were no reportable occurrences reported during the year to the NRC as required by Technical Specification 8.2.4(b).

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