ML081650347
| ML081650347 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 06/11/2008 |
| From: | Constellation Energy Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| TAC MD5928, TAC MD5929 | |
| Download: ML081650347 (6) | |
Text
Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, Maryland 20657 Constellation Energy-Nuclear Generation Group June 11, 2008 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:
SUBJECT:
Document Control Desk Calvert Cliffs Nuclear Power Plant Unit Nos. 1 & 2; Docket Nos. 50-317 & 50-318 Additional Information re: Control Room Habitability (TAC Nos. MD5928 and MD5929)
(a)
Letter from Mr. J. A. Spina (CCNPP) to Document Control Desk (NRC),
dated March 12, 2008, Response to Request for Additional Information re:
Control Room Habitability (TAC Nos. MD5929 and MD5929)
REFERENCES:
(b)
Letter from Mr. J. E. Pollock (CCNPP) to Document Control Desk (NRC),
dated June 29, 2007, License Amendment Request:
Revise Technical Specifications Regarding Control Room Habitability in Accordance with TSTF-448 Using the Consolidated Line Item Improvement Process In Reference (a) we provided additional information as requested by the Nuclear Regulatory Commission (NRC) staff to support our request to modify Technical Specification requirements for the Control Room emergency ventilation system in accordance with Technical Specification Task Force-448, Revision 3. In Reference (a), we provided a new markup of Technical Specification 5.5.17, Control Room Envelope Habitability Program which added an inspection of the Control Room Envelope boundary as Technical Specification 5.5.17.d. After further consideration and interactions with the NRC staff, we are modifying Technical Specification 5.5.17.d as shown on the attached markup.
Attachment (1) provides a revised markup of proposed Technical Specification 5.5.17 that includes a revised section (d). Please replace previous versions of proposed Technical Specification 5.5.17 with the attached markup. No Technical Specification Bases are provided for this section. This information does not alter the No Significant Hazards Determination provided in Reference (b).
Document Control Desk June 11, 2008 Page 2 Should you have questions regarding this matter, please contact Mr. Jay S. Gaines at (410) 495-5219.
Very truly yours, STATE OF MARYLAND TO WIT:
COUNTY OF CALVERT I, Douglas R. Bauder, being duly sworn, state that I am Plant General Manager - Calvert Cliffs Nuclear Power Plant, Inc. (CCNPP), and that I am duly authorized to execute and file this License Amendment Request on behalf of CCNPP. To the best of my knowledge and belief, the statements contained in this document are true and correct.
To the extent that these statements are not based on my personal knowledge, they are based upon information provided by other CCNPP employees and/or consultants.
Such information has been reviewed in accordance with company pract' an I believe it to be reliable.
Subscribed and sworn before me, a Notary Public in and for the State of Maryland and County of QV.
, this I I day of jI_
,2008.
"WITNESS my Hand and Notarial Seal:
?l" ublic My Commission Expires:
II[IO Date DRB/PSF/bjd
Attachment:
(1)
Revised Markup of Technical Specification 5.5.17 cc:
D. V. Pickett, NRC Resident Inspector, NRC S. J. Collins, NRC S. Gray, DNR
ATTACHMENT (1)
REVISED MARKUP OF TECHNICAL SPECIFICATION 5.5.17 Calvert Cliffs Nuclear Power Plant, Inc.
June 11, 2008
Programs an'd 'Manualas
,5.5
- 5.
5 Programs and 'Manuals
- b.
Ai-r 1,-oc~k testiilng accepta:nce c~riteria are:.
- 1.
Ov'eralll ai:,r lock leakage rate. i.s
- 0.,05 L, when tested
,at -P-:
Pall
- 2.
For each door, Teakage rate is 0.00,02 L, when pressurized,to 15 psig.,
The provi:s.ions of SR. 3.,O.2 do not apply to. the te~stý frequencies, specified in the Containment Leakage Rate Testing P'rogram.
The. provision's of SR 3..0.3 are applicable to the Containment, Leakage R#ate Testin g Programý A-CAL'VERT CLIFFS-UNIT I CALVERT CLIFFS,-
UN1IT 2 5.5-18:
,Amendme'nt No".
27T8 Amendment N~o, 255
Insert 2 5.5.17 Control Room Envelope Habitability Program A Control Room Envelope (CRE)
Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Emergency Ventilation System (CREVS),
CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a' smoke challenge.
The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of 5 rem whole body or its equivalent to any part of the body for the duration of the accident.
The program shall include the following elements:
- a.
The definition of CRE and the CRE boundary.
- b.
Requirements for maintaining CRE boundary in its design condition including configuration control and preventive maintenance.
- c.
Requirements for (i) determining the unfiltered air inleakage past the CRE boundary into the CRE in accordance with the testing methods and at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and (ii) assessing CRE habitability at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0.
- d.
License controlled programs will be used to verify the integrity of the CRE boundary.
Conditions that generate relevant information from those programs will be entered into the corrective action process and shall be trended and used as part of the 36 month assessments of the CRE boundary.
- e.
The quantitative limits on unfiltered air inleakage into the CRE.
These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph c.
The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences.
Unfiltered air inleakage limits for hazardous
chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis.
- f.
The provisions of SR 3.0.2 are applicable to the Frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and assessing the CRE boundary as required by paragraphs c and d respectively.