ML20133B963
| ML20133B963 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 09/30/1985 |
| From: | Denton, Denton R BALTIMORE GAS & ELECTRIC CO. |
| To: | Butcher E Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8510070173 | |
| Download: ML20133B963 (2) | |
Text
s.
q BALTIMORE G AS AND ELECTRIC COMPANY P.O. B O X 1475 B ALTIM OR E. M A R YLA N D 212o3 NUCLEAR POWER DEPARTMENT catvaar ctirrs nuctrAn powea
"'^NT September 30, 1985 LUSBY, M ARYLAND 20657 U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D. C. 20555 ATTENTION:
Mr. Edward J. Butcher, Jr., Acting Chief Operating Reactors Branch #3 Division of Licensing
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50-317 & 50-318 Request for Amendment
REFERENCES:
(a)
Letter from A. E. Lundvall, Jr., BG&E, to 3. R. Miller, NRC, dated April 26,1985, Request for Amendment Gentlemen:
Reference (a), Change No. 3, proposed a change to our Technical Specifications clarifying the Surveillance Requirements for Containment Tendon End Anchorages and Adjacent Concrete Surfaces. This letter provides supplemental information requested by the NRC concerning concrete surface inspections. Additionally, an expanded rewording of Surveillance Requirement 4.6.1.6.3, Containment Liner Plate, is also included.
In light of recent industry containment inspection results, containment surface surveillances have come under closer scrutiny by both the NRC and the nuclear industry as a whole. In conjunction with the administrative Technical Specification change in Reference (a), the NRC staff has recommended incorporating a portion of 10 CFR 50 Appendix 3.V.A. into the existing Liner Plate Surveillance. Both the existing surveillance and the proposed change are listed below:
EXISTING SURVEILLANCE:
4.6.1.6.3 Liner Plate. The structural integrity of the containment liner plate shall be determined during the shutdown for each Type A containment leakage rate test (Reference Specification 4.6.1.2) by a visual inspection of the plate and verifying no apparent changes in appearance or other abnormal degradation.
I e510070173 e50930 g/
ADOCK 0 % 3 7 j l PDR P
v 0
L
+
Mr. E. 3. Butcher September 30,1985 Page 2 PROPOSED CHANGE:
4.6.1.6.3 Containment Surfaces.
The exposed accessible interior ana exterior surfaces of the containment, including the liner plate, shall be visually inspected during the shutdown-for each Type A containment
' leakage rate test (Reference Specification 4.6.1.2). This inspection shall be performed prior to the Type A containment leakage rate test to uncover any evidence of structural deterioration which may affect either the containment structural integrity or leak-tightness.
This change does not add any additional requirements. Inspections of accessible interior
- and exterior containment surfaces are currently conducted prior to the Type A leakage rate tests.
Rather, this change supplements the existing Technical Specification containment surfaces inspection program by reiterating 10 CFR 50 Appendix 3.V.A.
requirements.
Recent industry experience with the failure of tendon anchor heads in a Containment Post-Tensioning System caused us to review our containinent surface surveillance test
-procedures.
This review indicated that appropriate measures are taken to locate apparent structural deterioration prior to pressurization for the Type A leakage rate tests. Our Integrated Leak Rate Test procedure states:
" Complete a general inspection of the accessible exterior surfaces of the containment structures and components. (This inspection is performed to uncover any evidence of visually obvious structural deterioration which may affect the containment's structural integrity.)"
Should you have further questions regarding the reply, we will be pleased to discuss them with you.
Very truly yours, i
m h
G4neral Supervisor-Training & Technical Services RED /BEH/sjb cc:
D. A. Brune, Esquire G. F. Trowbridge, Esquire
' D. H. Jaffe, NRC T. Foley, NRC T. Magette, DNR L
- - -