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| {{#Wiki_filter:-* ' ~* .. LJLJLJmanklin Research Center . Division of The Franklin Institute November 17, .. 1979 United States Nuclear Regulatory Commission Washington, D.C. 20555 Attention: | | {{#Wiki_filter:-* |
| Mr. Gary Zech Project Monitor | | ' ~* |
| | LJLJLJmanklin Research Center |
| | . ~ Division of The Franklin Institute November 17, .. 1979 United States Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Mr. Gary Zech Project Monitor |
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| ==Reference:== | | ==Reference:== |
| | FRC Project C5257 NRC Contract NRC~03-79-118 |
| | -NRC TAC No. 08638 FRC Task Nos. 50/51 |
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| FRC Project C5257 NRC Contract NRC~03-79-118 -NRC TAC No. 08638 FRC Task Nos. 50/51 Title: Surry Units 1 & 2; Containment Leak Rate Testing (App*endix J)
| | ==Title:== |
| | Surry Units 1 & 2; Containment Leak Rate Testing (App*endix J) |
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| ==Dear Mr. Zech:== | | ==Dear Mr. Zech:== |
| *A status .of the subject review package is_ provided in enclosure (1). It is forwarded to provide both the NRC and VEPCO with an opportunity to concur with or comment on the status as determined by the FRC. Enclosure (2) provides a listing of additional information required _by the FRC* to complete the*review.
| | |
| For your information, the milestone dates for review of this package are .as follows: * | | *A status .of the subject review package is_ provided in enclosure (1). |
| * Enc. SPC/cal . Receipt of Additional Information:.
| | It is forwarded to provide both the NRC and VEPCO with an opportunity to concur with or comment on the status as determined by the FRC. |
| 1/15/80 Start Final Review: 2/4/80 Submit Draft Report*to NRG: 3/31/80 Very truly yours, ,4'r7dcfr S. P. Carfagno Project Manager f xool s 11! The Benjamin Franklin Parkway, Philadelphia, Pa. 19103 (215) 448-1000 TWX-710 670 1889 Enclosure (1) STATUS OF IMPLEMENTATION 10 CFR 50, APPENDIX J SURRY 1 & 2 1.0 GENERIC ISSUE BACKGROUND . . Appendix J to 10 CFR 50 was published on February 14, 1973. Since several plants were either operating or in advanced stages of tion at the time, it was frequently not possible to implement the re~ quirements of Appencµ..x Jin these plants without exceptions. | | Enclosure (2) provides a listing of additional information required |
| During mid-1975, the USNRC requested all licensees concerned to review their status of compliance with Appendix J and to identify planned actions (design modifications, amendment to technical cations, requests for exemption pursuant to 10 CFR 50.12, etc.) where not in full compliance. | | _by the FRC* to complete the*review. |
| Subsequently, the NRC developed positions regarding the extent. to which leak testing practices generally satisfy the intent of the regulation. | | For your information, the milestone dates for review of this package are .as follows: * * |
| These positions have been utilized to resolve certain exemption or technical specification change requests for specific plants. The generic issue, however, has remained open primarily owing to proposed changes to both Appendix J and the ed concensus standards related to containment leak rate testing. The NRC presently intends to resolve all outstanding questions in *this area prior to October, 1980. The proposed regulatory or standards changes have developed sufficiently to preclude the precipitation by such action of further generic issues. Accordingly, a concerted effort has been scheduled to provide*a final review.of all outstanding requests. | | . Receipt of Additional Information:. 1/15/80 Start Final Review: 2/4/80 Submit Draft Report*to NRG: 3/31/80 Very truly yours, |
| This effort may require licencees to submit additional information necessary to resolve the specific issues for their plants. 2.0 SPECIFIC BACKGROUND According to the file of correspondence relating to implementation of Appendix J requirements for Surry, Units No. 1 and No. 2, the history of the issue is as follows: Virginia Electric and Power Company (VEPCO) replied to the NRC's generic letter (dated 8/4/75) on October 20, 1975. In that reply, VEPCO listed seven differerices between the then existing technical specifications and the approved version of Appendix J. VEPCO further stated that it would modify its program to.accommodate the technical differences with exception of the requirement to test the containment personnel air lock after each opening. Subsequently, VEPCO submitted Proposed Technical Specification Change No. 69 on September 22, 1978 which specified that Containment Leakage Testing would be performed in accordance with Appendix J except for the personnel hatch which would be tested at least quarterly instead of after each entry. | | ,4'r7dcfr S. P. Carfagno Project Manager Enc. |
| e e On January 9, 1979, in response to an NRC letter dated No~ember 29, 1978, VEPCO stated that it would conform to the NRC Staff's tion of the "after each opening" requirement of Appendix J for ment air locks. VEPCO further stated that air lock seals would be tested within 72 hours of each use to verify proper sealing and that the entire air lock would be tested at peak calculated accident pressure at intervals of no more then six months. Finally, on September 24, 1979, VEPCO amended its Proposed Technical Specification Change No. 69 to replace the reference volume method of leakage rate testing with the absolute method of leakage rate testing of ANSI N45 .4-1972. I 3.0 OUTSTANDING ISSUES .. The outstanding requests, questions or issues as enumerated in the correspondence listed above relating to implementation of Appendix J criteria for SURRY .Units 1 and 2 which require review, comment or approval are: ITEM 1 4.0 INFORMATION REQUIRED DESCRIPTION OF ISSUE Acceptance of T.-S. Change No. 69 with amendment of 9/24/79 (contingent upon further amendment to include VEPCO's commitment of 1/9/79). In order to *conduct a final review in this matter, additional mation, docmnentation or drawings is needed as listed in enclosure (2). Additionally, should the licensee have a substantial disagreement with either the.background or listing of outstanding issues described above, or have other information pertinent to a final review and disposition of this matter, this should be made known at this time. It is desired that all information indicated herein be provided within approximately thirty days. | | SPC/cal xool s |
| ' . Item 1 2 3 4 Enclosure (2) Additional Information Required ** -. **-=-Description_
| | f 11! |
| Further description of the method to be used to verify proper seating of air lock seals with 72 hours of opening, including system diagram, !test pressures and system discription. | | The Benjamin Franklin Parkway, Philadelphia, Pa. 19103 (215) 448-1000 TWX-710 670 1889 |
| Manufacturer's drawings or other drawings of the personnel air lock showing sealing devices and door operating/locking mechanisms, as well as the manufacturer's recommended test pressure. | | |
| A description of how L will be determined (para 4.(a)(iii) of Ap~. J.) in view of the fact the method of performing the Type A test was changed from the reference volume method to the absolute pressure method. A further description of the "make up air method" to be used to verify the Type A test discussed in VEPCO's 9/24/79 letter.}} | | Enclosure (1) .. |
| | STATUS OF IMPLEMENTATION 10 CFR 50, APPENDIX J SURRY 1 & 2 1.0 GENERIC ISSUE BACKGROUND Appendix J to 10 CFR 50 was published on February 14, 1973. Since several plants were either operating or in advanced stages of construc-tion at the time, it was frequently not possible to implement the re~ |
| | quirements of Appencµ..x Jin these plants without exceptions. |
| | During mid-1975, the USNRC requested all licensees concerned to review their status of compliance with Appendix J and to identify planned actions (design modifications, amendment to technical specifi-cations, requests for exemption pursuant to 10 CFR 50.12, etc.) where not in full compliance. Subsequently, the NRC developed positions regarding the extent. to which leak testing practices generally satisfy the intent of the regulation. These positions have been utilized to resolve certain exemption or technical specification change requests for specific plants. The generic issue, however, has remained open primarily owing to proposed changes to both Appendix J and the associat-ed concensus standards related to containment leak rate testing. |
| | The NRC presently intends to resolve all outstanding questions in |
| | *this area prior to October, 1980. The proposed regulatory or standards changes have developed sufficiently to preclude the precipitation by such action of further generic issues. Accordingly, a concerted effort has been scheduled to provide*a final review.of all outstanding requests. |
| | This effort may require licencees to submit additional information necessary to resolve the specific issues for their plants. |
| | 2.0 SPECIFIC BACKGROUND According to the file of correspondence relating to implementation of Appendix J requirements for Surry, Units No. 1 and No. 2, the history of the issue is as follows: |
| | Virginia Electric and Power Company (VEPCO) replied to the NRC's generic letter (dated 8/4/75) on October 20, 1975. In that reply, VEPCO listed seven differerices between the then existing technical specifications and the approved version of Appendix J. VEPCO further stated that it would modify its program to.accommodate the technical differences with exception of the requirement to test the containment personnel air lock after each opening. Subsequently, VEPCO submitted Proposed Technical Specification Change No. 69 on September 22, 1978 which specified that Containment Leakage Testing would be performed in accordance with Appendix J except for the personnel hatch which would be tested at least quarterly instead of after each entry. |
| | |
| | e e On January 9, 1979, in response to an NRC letter dated No~ember 29, 1978, VEPCO stated that it would conform to the NRC Staff's interpreta-tion of the "after each opening" requirement of Appendix J for contain-ment air locks. VEPCO further stated that air lock seals would be tested within 72 hours of each use to verify proper sealing and that the entire air lock would be tested at peak calculated accident pressure at intervals of no more then six months. |
| | Finally, on September 24, 1979, VEPCO amended its Proposed Technical Specification Change No. 69 to replace the reference volume method of leakage rate testing with the absolute method of leakage rate testing of ANSI N45 .4-1972. I 3.0 OUTSTANDING ISSUES |
| | ..The outstanding requests, questions or issues as enumerated in the correspondence listed above relating to implementation of Appendix J criteria for SURRY .Units 1 and 2 which require review, comment or approval are: |
| | ITEM DESCRIPTION OF ISSUE 1 Acceptance of T.-S. Change No. 69 with amendment of 9/24/79 (contingent upon further amendment to include VEPCO's commitment of 1/9/79). |
| | 4.0 INFORMATION REQUIRED In order to *conduct a final review in this matter, additional infor-mation, docmnentation or drawings is needed as listed in enclosure (2). |
| | Additionally, should the licensee have a substantial disagreement with either the.background or listing of outstanding issues described above, or have other information pertinent to a final review and disposition of this matter, this should be made known at this time. |
| | It is desired that all information indicated herein be provided within approximately thirty days. |
| | |
| | Enclosure (2) ** |
| | Additional Information Required Item Description_ |
| | 1 Further description of the method to be used to verify proper seating of air lock seals with 72 hours of opening, including system diagram, !test |
| | **-=- |
| | pressures and system discription. |
| | 2 Manufacturer's drawings or other drawings of the personnel air lock showing sealing devices and door operating/locking mechanisms, as well as the manufacturer's recommended test pressure. |
| | 3 A description of how L will be determined (para 4.(a)(iii) of Ap~. J.) in view of the fact the method of performing the Type A test was changed from the reference volume method to the absolute pressure method. |
| | 4 A further description of the "make up air method" to be used to verify the Type A test discussed in VEPCO's 9/24/79 letter.}} |
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ML20210Q7661999-08-0606 August 1999 Requests Exception to 10CFR50.4 Requirement to Provide Total of Twelve Paper Copies When Submitting Surry & North Anna UFSAR Updates.Seek Approval to Submit Only Signed Original & One CD-ROM Version,Per Conversation with J Skoczlas ML18152B4091999-08-0505 August 1999 Forwards Vepc semi-annual fitness-for-duty Program Performance Data Rept for 990101-990630,IAW 10CFR26.71(d) ML18152B4001999-07-29029 July 1999 Requests Relief from Certain Impractical Requirements of ASME Section XI Code Associated with Partial Exams Conducted During 1998 Surry Unit 1 Refueling Outage.Relief Request SR-020 Encl ML18152B3981999-07-28028 July 1999 Forwards 60-day Response to GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Commitments Contained in Ltr,Listed ML18152B3971999-07-26026 July 1999 Provides Estimates of Licensing Actions Expected to Be Submitted in Fys 2000 & 2001,in Response to NRC AL 99-02 ML18151A6281999-07-23023 July 1999 Forwards Revised Epips,Including Rev 19 to EPIP-4.02,rev 14 to EPIP-4.16,rev 8 to EPIP-4.21 & Rev 7 to EPIP-4.30.EP & EPIPs Continue to Meet Stds of 10CFR50.47(b) ML18152B3991999-07-23023 July 1999 Requests That License for Jz Laplante Be Canceled as License Is No Longer Required ML18152B3961999-07-23023 July 1999 Forwards Preliminary,Uncertified License Application & Medical Certification for License to Operate Surry Power Station Units 1 & 2 for Ds Cobb.Encl Withheld,Per 10CFR2.790 (a)(6) ML18152B3931999-07-16016 July 1999 Forwards Updated NRC Form 396 & Ltr,Which Documents Medical Status of Mb Gross,License SOP-20476-2.Encl Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML18152B4401999-07-0101 July 1999 Informs NRC That on 990511,Dominion Resources,Inc,Executed Amended & Restated Agreement & Plan of Merger with Consolidated Natural Gas Co ML18152B4371999-06-24024 June 1999 Forwards Response to NRC Request for Clarification of Relief Requests Submitted on 990212,requesting Relief from Performing Hydrostatic Testing for Certain Small Diameter Class 1,RCS Pressure Boundary Connections ML18152B4361999-06-22022 June 1999 Forwards Response to RAI Re Surry & North Anna Power Stations,Units 1 & 2,per GL 96-06 ML18152B4301999-06-0303 June 1999 Informs of Util Intention to Revise Schedule for Submittal of License Renewal Applications for Surry & North Anna Power Stations to March 2002 ML18152B4261999-05-28028 May 1999 Provides Formal Notification of Effect of Recent Organizational Restructuring on OLs of North Anna & Surry Power Stations,Per NRC 990513 Telcon Request ML18152B4221999-05-27027 May 1999 Forwards Info Concerning Changes to ECCS Evaluation Models & Application in Existing Licensing Analyses for Surry & North Anna Power Stations,Units 1 & 2 ML18152B4231999-05-26026 May 1999 Informs That Vepc Will Revise 180 Day Response to NRC GL 96-05,within 120 Days of Date of Ltr to Incorporate Commitment to Participate in Joint Owners Group Program as Applicable ML18152B4211999-05-25025 May 1999 Forwards Rev 1 to Relief Request P-11 to Clarify Original Intent of Request by Specifically Requesting Relief from Requirements of Section 6.1 of OM-6 ML18152B4171999-05-17017 May 1999 Provides Notification of Number of Steam Generator Tubes That Were Plugged During Spring 1999 Refueling Outage Planned ISI ML18152A3701999-05-13013 May 1999 Submits Proposal to Use Provisions of ASME Section XI Code Case N-597 for Analytical Evaluation of Class 1,2 & 3 Carbon & Low Alloy Steel Piping Components Subjected to Wall Thinning as Result of Flow Accelerated or Other Corrosion ML18152B4121999-05-0303 May 1999 Forwards Application for Renewal of License for SV Ross. Encl Withheld Per 10CFR2.790(a)(6) ML18152B4101999-04-29029 April 1999 Forwards Scope & Objectives for 990803 Surry Power Station Emergency Exercise.Without Encls ML18152B6561999-04-23023 April 1999 Forwards Annual Radioactive Effluent Release Rept for Surry Power Station,Jan-Dec 1998, Which Includes Summary of Quantities of Radioactive Liquid & Gaseous Effluents & Solid Waste Released During CY98 ML18152B6491999-04-13013 April 1999 Forwards MOR for Mar 1999 for Surry Power Station,Units 1 & 2.MOR for Feb 1999 Incorrectly Stated Gross Electrical Energy Generated (Mwh) for Unit 2.Rept Should Have Stated Monthly Figure as 568965.0 ML18151A5851999-03-31031 March 1999 Forwards Rept on Status of Decommissioning Funding for Each of Four Nuclear Power Reactors,Per 10CFR50.75(f)(1) ML18152A2801999-03-30030 March 1999 Forwards Summary of Structural Integrity Evaluation of Thermally Induced Over Pressurization of Containment Penetration Piping During DBA for SPS & Naps,Units 1 & 2,per GL 96-06.Draft Proposed UFSAR Revised Pages,Encl ML18153A2721999-03-29029 March 1999 Forwards LER 99-002-00 Per 10CFR50.73.Listed Commitments Contained in Ltr ML18153A3421999-03-26026 March 1999 Provides Updated Medical Status Rept for Wb Gross in Accordance with License SOP-20476-02,Docket 55-5228,as Amended by 980320 License Amend.Informs That Gross Exhibits No Performance Problems & Will Continue on Current Medicine ML20204H0331999-03-17017 March 1999 Forwards Rev 5 to PSP for Surry & North Anna Power Stations & Associated Isfsis.Description & Justification for Changes Included with Plan Rev.Rev 5 to PSP Withheld Per 10CFR73.21 ML18153A3411999-03-15015 March 1999 Forwards Signed Applications & Medical Certificates for Initial License at Surry Power Station Units 1 & 2 for Listed Individuals.Without Encls 1999-09-08
[Table view] Category:RESEARCH INSTITUTION/LABORATORY TO NRC
MONTHYEARML18151A0641987-09-0808 September 1987 Forwards Comments on Review of Plant Scenario.Scenario Should Support Reasonable Demonstration of Licensee Emergency Response Capability.No Major Deficiencies Noted ML20206J6001986-08-0808 August 1986 Advises That NUREG-0956 Support Calculations Using ORNL Trends Code to Evaluate Influence of Containment Chemistry or Retention of Hi Can Also Provide Useful Info for General NUREG-1150 Issue Paper,Per Telcon Discussion ML20206H1131986-06-23023 June 1986 Submits DHEAT2 Parametric Calculations for Plant,Per 860620 Discussions.Calculations Run Assuming Any Steam Spike Would Develop Too Slowly to Contribute to DCH Peak Pressure ML18143B3621985-07-17017 July 1985 Responds to Request for Estimate of Probability That Break Outside Containment During V Sequence at Facility Will Be Submerged.Best Estimate Probability Lies Between 50% & 90%, Depending on Operator Reaction.Lpsi Sys Diagrams Encl ML20133N7721985-03-27027 March 1985 Forwards Info Telecopied on 850325 Re Locational Distribution of Three Fission Product Species for Surry V Sequence & Time Dependent Release for Fission Product Groups for Peach Bottom ML20134A1011985-02-20020 February 1985 Submits Results of Noble Gas Release Sequences Using March Code for Facilities ML20133N3461985-02-20020 February 1985 Discusses Review of March Results for Surry & Peach Bottom Sequences,In Order to Quantify Expected Noble Gas Releases. March Model Appropriate for Behavior of Noble Gases ML20128N6571984-02-22022 February 1984 Comments on Draft Vols IV-VI of BMI-2104,presented at Peer Review 840126 & 27 Meetings.Comments Concern Completed Calculations for Sequoyah Ice Condenser Plant,Recalculated Surry Results & Completed Calculations for Zion Plant ML19340B1271980-10-17017 October 1980 Forwards 800501 Evaluation of Revised Facility Emergency Plan.Plan Is Well Written & Addresses Objectives in Logical & Comprehensive Manner.Suggestions Not Considered Deficiencies.Included as Proposals for Addl Clarification ML19332A4411980-09-0808 September 1980 Submits Info Re Diesel Generator Status Annunciation Sys Requirements Contained in IEEE Std 279-1971.Corrective Actions Required Re Disabling & Nondisabling Conditions ML18136A1881979-10-12012 October 1979 Forwards Status Rept Re Containment Leak Rate Test & Request for Addl Info to Complete Review ML18130A6291979-08-28028 August 1979 Discusses Proposed Fire Protection SER Review.Recommends Further Evaluation of Section Re Electrical Valve Supervision on Valves Controlling Fire Water Sys & Sectionalizing Valves 1987-09-08
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LJLJLJmanklin Research Center
. ~ Division of The Franklin Institute November 17, .. 1979 United States Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Mr. Gary Zech Project Monitor
Reference:
FRC Project C5257 NRC Contract NRC~03-79-118
-NRC TAC No. 08638 FRC Task Nos. 50/51
Title:
Surry Units 1 & 2; Containment Leak Rate Testing (App*endix J)
Dear Mr. Zech:
- A status .of the subject review package is_ provided in enclosure (1).
It is forwarded to provide both the NRC and VEPCO with an opportunity to concur with or comment on the status as determined by the FRC.
Enclosure (2) provides a listing of additional information required
_by the FRC* to complete the*review.
For your information, the milestone dates for review of this package are .as follows: * *
. Receipt of Additional Information:. 1/15/80 Start Final Review: 2/4/80 Submit Draft Report*to NRG: 3/31/80 Very truly yours,
,4'r7dcfr S. P. Carfagno Project Manager Enc.
SPC/cal xool s
f 11!
The Benjamin Franklin Parkway, Philadelphia, Pa. 19103 (215) 448-1000 TWX-710 670 1889
Enclosure (1) ..
STATUS OF IMPLEMENTATION 10 CFR 50, APPENDIX J SURRY 1 & 2 1.0 GENERIC ISSUE BACKGROUND Appendix J to 10 CFR 50 was published on February 14, 1973. Since several plants were either operating or in advanced stages of construc-tion at the time, it was frequently not possible to implement the re~
quirements of Appencµ..x Jin these plants without exceptions.
During mid-1975, the USNRC requested all licensees concerned to review their status of compliance with Appendix J and to identify planned actions (design modifications, amendment to technical specifi-cations, requests for exemption pursuant to 10 CFR 50.12, etc.) where not in full compliance. Subsequently, the NRC developed positions regarding the extent. to which leak testing practices generally satisfy the intent of the regulation. These positions have been utilized to resolve certain exemption or technical specification change requests for specific plants. The generic issue, however, has remained open primarily owing to proposed changes to both Appendix J and the associat-ed concensus standards related to containment leak rate testing.
The NRC presently intends to resolve all outstanding questions in
- this area prior to October, 1980. The proposed regulatory or standards changes have developed sufficiently to preclude the precipitation by such action of further generic issues. Accordingly, a concerted effort has been scheduled to provide*a final review.of all outstanding requests.
This effort may require licencees to submit additional information necessary to resolve the specific issues for their plants.
2.0 SPECIFIC BACKGROUND According to the file of correspondence relating to implementation of Appendix J requirements for Surry, Units No. 1 and No. 2, the history of the issue is as follows:
Virginia Electric and Power Company (VEPCO) replied to the NRC's generic letter (dated 8/4/75) on October 20, 1975. In that reply, VEPCO listed seven differerices between the then existing technical specifications and the approved version of Appendix J. VEPCO further stated that it would modify its program to.accommodate the technical differences with exception of the requirement to test the containment personnel air lock after each opening. Subsequently, VEPCO submitted Proposed Technical Specification Change No. 69 on September 22, 1978 which specified that Containment Leakage Testing would be performed in accordance with Appendix J except for the personnel hatch which would be tested at least quarterly instead of after each entry.
e e On January 9, 1979, in response to an NRC letter dated No~ember 29, 1978, VEPCO stated that it would conform to the NRC Staff's interpreta-tion of the "after each opening" requirement of Appendix J for contain-ment air locks. VEPCO further stated that air lock seals would be tested within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of each use to verify proper sealing and that the entire air lock would be tested at peak calculated accident pressure at intervals of no more then six months.
Finally, on September 24, 1979, VEPCO amended its Proposed Technical Specification Change No. 69 to replace the reference volume method of leakage rate testing with the absolute method of leakage rate testing of ANSI N45 .4-1972. I 3.0 OUTSTANDING ISSUES
..The outstanding requests, questions or issues as enumerated in the correspondence listed above relating to implementation of Appendix J criteria for SURRY .Units 1 and 2 which require review, comment or approval are:
ITEM DESCRIPTION OF ISSUE 1 Acceptance of T.-S. Change No. 69 with amendment of 9/24/79 (contingent upon further amendment to include VEPCO's commitment of 1/9/79).
4.0 INFORMATION REQUIRED In order to *conduct a final review in this matter, additional infor-mation, docmnentation or drawings is needed as listed in enclosure (2).
Additionally, should the licensee have a substantial disagreement with either the.background or listing of outstanding issues described above, or have other information pertinent to a final review and disposition of this matter, this should be made known at this time.
It is desired that all information indicated herein be provided within approximately thirty days.
Enclosure (2) **
Additional Information Required Item Description_
1 Further description of the method to be used to verify proper seating of air lock seals with 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of opening, including system diagram, !test
pressures and system discription.
2 Manufacturer's drawings or other drawings of the personnel air lock showing sealing devices and door operating/locking mechanisms, as well as the manufacturer's recommended test pressure.
3 A description of how L will be determined (para 4.(a)(iii) of Ap~. J.) in view of the fact the method of performing the Type A test was changed from the reference volume method to the absolute pressure method.
4 A further description of the "make up air method" to be used to verify the Type A test discussed in VEPCO's 9/24/79 letter.