View source for NSD-NRC-97-5379, Forwards Responses & Ssar Revs to Address Three FSER Open Items Re Environmental Qualification of Mechanical & Electrical Equipment.W Status for Items 270.16F & 270.17F Will Be Changed to Confirm W Pending Formal Ssar Rev

{{Adams
| number = ML20212A840
| issue date = 10/14/1997
| title = Forwards Responses & Ssar Revs to Address Three FSER Open Items Re Environmental Qualification of Mechanical & Electrical Equipment.W Status for Items 270.16F & 270.17F Will Be Changed to Confirm W Pending Formal Ssar Rev
| author name = Mcintyre B
| author affiliation = WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
| addressee name = Quay T
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05200003
| license number = 
| contact person = 
| document report number = NSD-NRC-97-5379, NUDOCS 9710270020
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 4
}}

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                       .                                                                C y-Westinghouse                Energy Systems                                     au 355 Pinsburgh Pemsylvania 15230-0355 Electric Corporation DCP/NRC1083 NSD-NRC-97 5379 Docket No.: 52-003
          .                                                                                          October 14, 1997
          - Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: T. R. QUAY

==SUBJECT:==
CllAPTER 3 FSER OPEN ITEMS

==Dear Mr. Quay:==

In a {{letter dated|date=October 9, 1997|text=letter dated October 9,1997}}, the NRC provided a list of FSER open items related to environmental qualification of mechanical and electrical equipment. Attached are the responses and SSAR revisions to address three of the items.
The source term question (270.15F, OITS #6027) from the {{letter dated|date=October 9, 1997|text=October 9,1997, letter}} will be addressed as part of Key issue 7. Key issue 7 is related to Chapter 15 radiological dose assessment.
The Westinghouse status for items 270.16F and 270.17F (OITS #'s 6028 and 6029) will be changed to Confirm W pending the fonnal SSAR revision. The Westinghouse status for item 270.18F (OITS#
6030) will be changed to Action N.
Please contact D. A. Lindgren at (412) 374-4856 with any questions.
A Brian A. McIntyre. Manager Advanced Plant Satuty and Licensing jml i
Attachment (U0y
          . cc: J. M. Sebrosky, NRC (w/ Attachment)                                                                              .l N. J. Liparulo, Westinghouse (w/o Attachment) 9710270020 97101(
PDR A-ADOCK 05200003                                                                                        -
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NRC REQUEST FOR ADDITIONAL INFORMATION Question 270.16F Radiation dose and blowout panel, Open item 3.11.3.13 OITS #6028 In SSAR Appendix 3D, Section 3D.5.5.1.1 reference is made to Attachment A, Section 1.7.4, the staff cannot locate this section in Attachment A, therefore Westinghouse should provide Section 1.7.4 of Attachment A for staff review. Note 5 of Table 3D.5 4 states,"A blowout panel is designed to open when the pressure difference exceeds 10 inches water gauge." It is the staffs understanding the design has changed and the blowout panel will activate on temperature. Westinghouse should make a correction to note 5 of Table 3D.5-4. These issues are collectively Open Item 3.11.3.1-3.
Response:                                                                                    .
The reference to 1.7.4 is a typographical error. The correct reference for radiation dose in Attachment A of Appendix 3D is 1.8.4, This will be corrected in Revision 17 of the SSAR. Please note that Attachment A is the format of a document to be completed by the Combined License applicant.
The reference to the blowout panel will be changed to a relief panel in Revision 17 of the SSAR.
 ,            SSAR Revision:
The tenth paragraph of subsection 3D.5.5.1.1 will be revised as follows:
The total integrated dose of radiation employed for testing is a combination of normal and design basis event dose, as applicable. It is defined to equal or exceed the raaximum radiation dose contained in the specification (Attachment A, Section l$7.4.). A margin of 10 percent is included in defining the total integrated dose for testing. Normal operating and design basis event gamma doses are simulated using a cobalt 60 source. The test dose is applied at a rate approximate to the initial phase of the design basis event dose rate shown in Figure 30.5-2 as modified by shielding etTects (typically 0.2 to 0.25 Mr/hr).
Note 5 of Table 3D.5-4 will be revised as follows:
: 5. A (efffb!c" rut panel is designed to open when the Mpfjjffejff[rp' er"'e
                          ,perr - r exceeds ggf!^ "~             -*r   ;; r;;-
W westingtiouse

I
    - kRC REEUEST FOR ADDITIONAL INFORMATION Question 270.17F GDC 11 and 17. Open item 3.11.3.1-4 OITS # 6029 Equipment that is used to perform a necessary safety function must be demonstrated to be capable of maintaining functional operability under all service conditions postulated to occur during its installed life, for the time it is required to operate. This requirement, which is embodied in GDC 1 and GDC 4, and Criteria III, XI, and XVII of Appendi,4 B to 10 CFR Pan 50, is applicable to equipment located inside and outside the containment. In SSAR Section 3.11.2.1 and in 3D.4 of Appendix 3D, the AP600 design is committed to GDCs 1,2,4 and 23, and Section 111 of 10 CIK Part 50, Appendix B.
However,in accordance with both SRP Section 3.1111 and Rev. I of RG 1.89, a commitment to Criteno ; XI regarding test cor, trol, and Criterion XVII regarding quality assurance records, of Appendix B to 10 CFR Part 50 should also be made. Therefore, this is Open Item 3.11.3.1-4

===Response===
The AP600 quality assurance program is in compliance with the criteria of 10 CFR Appendix B.
Specific reference to Criteria XI and XVII will be added as noted below.
SSAR Revision:
Revise the fourth paragraph of subsection 3.11.2.1 as follows:
Regulatory guides providing guidance for meeting the requirements of 10CFR50, General Design Criteria 1,4,23, and 50; Appendix B, Criterifen-III2KIEd$djXMAppe     Q to 10CFR50 and 10CFR50.49, include Regulatory Guide 1.89, Regulatory Guide 1.30, Regulatory Guide 1.63, Regulatory Guide 1.73 Regulatory Guide 1.100, and Regulatory Guide 1.131. The maintenance surveillance program follows the guidance of Regulatory Guide 1.33.
Revise the second Paragraph of subsection 3D.4 as follows:
He qualification methods described in this appendix are used to verify the environmental design basis and capability of the safety-related electrical and mechanical equipment supplied for the AP600. The results of the verification, as well as the design basis for each equipment, is documented in an uipment qualification data package. (See Attachment A for sample format.)
Design controlf"'$$:sMM2$MfM[oiiYd'$M'MancsIleco'/d s               k@ is performed through the AP600 Quality Assurance Program. (See Chapter 17.)
270.17-1

       ,.      NRC REQUEST FOR ADDITIONAL INFORMATION n=  m
                                                                                                                     'i Question 270.18F Containment Spray Open items 3.11.3.1-15 OITS #6030 in SSAR Sections 3.11.4 and 3D.5.5.1.6 of Appendix 3D it is stated that there is no caustic containment spray in the AP600 Design. Westinghouse should verify the validity of this statement because the staff understands that the AP600 design has been changed to include a containmmt spray.
This is Open item 3.11.3.1-5.

===Response===
The statements in, Section 3.11 and Appendix 3D that there is no caustic spray remains valid with the-addition ofi nonsafety-related containment spray function for severe accident mitigation. Three points about the spray and pH control are peninent to this question. The containment spray is not intended for use during design basis accidents. The use of the containment spray is called for in severe accident management guidelines. The source of the water used in the containment spray is the fire protection water. This water receives limited treatment and is not caustic. Caustic compounds are not used for post accident pH control in the AP600. Tri sodium phosphate is used for post accident pH ,      '
control in the AP600.
SSAR Revisiont NONE 270.18-1}}