ML19254D800

Forwards Request for Addl Info Re Fsar.Requests Amend to FSAR Reflecting Responses by 791130

ML19254D800
Person / Time
Site:	Grand Gulf
Issue date:	10/19/1979
From:	Baer R Office of Nuclear Reactor Regulation
To:	Stampley N MISSISSIPPI POWER & LIGHT CO.
References
NUDOCS 7910300180
Download: ML19254D800 (7)

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[ UNITED STATES y '-l,. -gy jb NUCLEAR REGULATORY COMMISSION 7 g g;gg[,. f wAsHWGTON, D. C. 20555 5, %W J %,.....f CCT 1 e1979 Docket Nos. 50-416 and 50-417 "r. N. L. Stampley, ' lice President Production and Enaineering Mississippi Power and Ligilt Company ~ P. O. Box 1640 Jackson, Mississippi 39205

SUBJECT:

REQUESTS FOR ADDITIONAL INFORMATION (Grand Gulf Nuclear Station, Units 1 and 2) As a result of our review of the information contained in the Final Safety Analysis Report for the Grand Gulf Nuclear Station, Units 1 and 2, we have developed the enclosed requests for additional information. We request that you amend your Final Safety Analysis Report to reflect your responses to the enclosed requests by November 30, 1979. If you cannot meet this date, please advise us of the date you can meet as soon as possible so that we may consider the need to revise our review schedule. Please contact us iT you desire any discussion or clarification of the enclosed requests. Sincerely, f 4chW 0dn Robert L. Baer, Chief Light Water Reactors Branch No. 2 Division of Project Management e

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ENCLOSURE REQUESTS FOR ADDITIONAL INFORMATION GRAND GULF NUCLEAR STATION UNITS 1 AND 2 DOCKET NOS. 50-416 AND 50-417 3;<, ,p,

irs 423.0 OUALITY ASSURANCE AND OPEPATIONS e r 423.2F The response to iten 423.7 is not acceptable. icur plant's technical, (14.2) specifications '. ill require tnat ninor te ;crary changes to precedures covering test activities cf safety-related equipment nust be a:;rcred by tt,to Terbers of the plant n;nagement staff, at least cne of. hich holds a Senior Reactor Operator's License cn the affected unit. Since cost, if not all, startup tests affect safety-related systers, this requirement applies to startup test procedures. (It dces not apply to preoperational tests conducted before fuel leading.) However, FSAR Section 14.2.4 indicates that minor changes to startup test precedures may be made "on-the-spot" by t're tes t supervisor (,tho is not required to hold a Senice Reactor Oper'tcr's License). Modify Section 14.2.4 to show that -inor changes to :artuo test procedures will be made in accordance with your technic 1 specification requirerents. 123.29 The response to item 423.10 indicates that testing will be conducted (14.2) in accordance with Regulatory Guide 1.80, June 1974, with the exception listed on FSAR page 3A/1.30-1. Provide a description of this pre-operational test. 423.30 The responses to some sub-parts of item 423.12, regarding Regulatory .(14.2) Guide 1.62, are not acceptable. Provide the inforration requested beicw. l.e(2),1.e(5), i.e(6), l.e(7),1.e(3), l.e(10), l.e(ll), i.e(12), l. f(l ), l. f(2), l.g(l),1.j (3),1.J(16), l.J(17),1.l(8),1.n(l), 1.n(2),1.n(5),1.n(6),1.n(ll),1.n(14)(e) Your response states that these systems and components will be tested as a part of your Acceptance Testing Program. It is our position that these systems and components are important to safety and should, therefore, be included in your preoperational test program. Provide a summary description of each of these tests and either (1) include these tests in your preoperational test program, or (2) provide a description of the administrative controls for the Acceptance Testing Program. If you decide on option (2), provide a sufficiently detailed description to enable us to determine that the review of acceptance test procedures, conduct of the tests, and review of the test results are commensurate with those of your preoperational test program. l(b) Ycur response to this item does not address the leaktightness c# s' .::uees =ch cr-tect arcinecred sa'=:" features 'rca 'icC: ^ ~. ' i s 2 r ;;: iCf ^~a! I; ?e ~~ a;;.;?Pi-;e

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j... 3 1.h(e) Ycur response to this item regarding tanks.chicn support ECCS is garbled. Clarify your respe ',se. i.i(1), l. i(3), l.i(4), l.i(5), l.i(6), l.i(15), l.i (19) Verify that the structural integrity test as described in FSAR Secticn 3.3 and the ccntainment tests described in Section 6.2.6 are dcne as part of your precperational test program. i.i(21) Your response to this item states tha+ no contair, ment penetration coolers are used in your -lant design. Provide a description of a startup test tha: ;ill demonstrate that concrete terceratures surroun ing h t penetrations (e.g., main steam lines) do not exceed design limits. 1.j (9) The response states that testing of the feedwater leakage control system will be added to preoperaticnal test description t'o. 5, " Residual Heat Removal System Preoperational Test." Modify the test description to describe this testing. 1.m(3) Your response states that fuel pool leak detection and sectionalizing devices test will be conducted as part of the fuel pool cooling and cleanup system preoperational test (22). Modify the test description to describe this testing. 4.m Your response states that a leakage demonstration of the MSIV leakage control system is conducted as precperational test No. 9. Apparently this test will be conducted at cold conditions. Provide a description of a test which demonstrates that the MSIV-LCS components operate properly when handling steam and that the system can handle the amount of leakage that is preSent when the main steam system is at operating temperature. ~ 5.c.c. Your response does not address the liquid radwaste system. Provide a description of your startup test which demonstrates the processing of liquid radioactive wastes. 423.31 Your response to item 423.13 is not totally acceptable. Provide the (14.2) infor ation recuested below. ~

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l, ~ ~ K;. - g 2. Traversing Incore Probe (TIP) System Preco: rational Test (la) - Modify the test description to delete the 'ccettance criterion addressing the squib charge. 3. Standby Service '.-later (SSW) System Preoperaticr.51 Test (26) - Your response indicates that the lesktightness of valves that isolate the SSW system frca other systems is acdressed in the revised test description. Ho.;ever, this is not adcressed by the test description. Excand the description to state how ycu will demonstrate the leaktightness of the valves which isolate the SSW system frcm the plant service war - system and the component cooling water system. 4. Class lE 125 Volt DC System Precperational Test (39) - Your response states that nreoperational test No. 44 deronstrates that the DC system loads are in accordance with battery sizing assumptions. However, it is not clear how this will be demon-strated. Modify the test description to state that the DC system load will be measured and verified to be consistent with battery sizing assumptions. Your response also refers to the response to item 041.31(f) for the minimum voltage demonstration. The response to item 041.31(f) does not state that the DC loads will be demonstrated'to be operable at minimum voltage levels, it only states that the DC equipment is "specified" for operation over a range of 105 to 140 volts. It is our position that you demon-strate the operability of the DC system loads at the minimum voltage level at whicn they can be po.itulated to operate. Modify the. test description to describe this demonstration. 423.32 Your response to item 423.14 addressing several startup test descriptions (14.2) is not totally acceptable. Provide the information requested below. 1. Mair Steam Line Isolation Valves (25) - Your response stated thet acceptance criteria for relief valve reset pressures are ~ contained, "if applicable," in STI-26. It is our position that y ou demonstrate during your initial test program that the relief valves reclose at the correct pressures. Modify this test description (or other test descriptions as necessary) to state that the test procedure will contain acceptance criteria for relief v31ve reset cressure. -;.7- - (;; 3 ; - y,, 9 2, 7:. e.;; g

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s M C M g;. 3. Recirculation System (30) - Modify the test descrip;icn to (a) provide acceptance criteria for speed of the re:irculat :n ou s d (folicwing trip of the normal supply breaker).'ec the L "3 set breaker closes, (b) provide acceptance criteria for pump startup rates that are consistent with assuJ.ptions of FEA i Secticr 15.4.0, and (c) describe how you will verify that no ca/itation occurs at allowable paier and flow conditions. 4 Loss of Turbine-Generator and Offsite Fc.;er (31' The itss cf turbine-generator and offsite pcwer should be riintEinec for a period of time sufficient to demonstrate that tre necessary equipment, controh, and instrumentation are available following station blackout to remove decay heat from the core using cnly emergency power supplies. It is our pcsition that you maintain the loss of offsite pcwer for at least 30 ninutes in order to demonstrate this. Modify the test description to state that offsite power will not be restored for at least 30 minutes. 423.33 Your response to item 423.15 indicates that FSAR Table 14.2-3 has been (14.2) modified to show that the MSIV full isolation will be conducted at Test Condition 6. On the contrary, this table still indicates that this demor.stration may be performeo at "anywhere) 75'. pc.;er." Modify the table to indicate that the full isolation will be demonstrated at Test Condition 6. 423.34 Your response to item 423.22 addresses preoperational tests. The item (14.2) refers to post-fuel loading tests. Revise your response to item 423.22 to address only post-fuel loading startup tests (precritical tests, initial criticality, low-power tests, and power ascension tests). - ~423.35 Your response to item 423.23 does not completely satisfy our require-(14.2) ments regarding the heat removal capability of ventilation systems serving areas that house engineered safety features. It is not apparent that post-accident design heat leads will be produced 9 ESF. equipment rooms during the power ascension test phase; therefore, simply assuring that area temperatures remain within design limits during this period will probably not demonstrate the design heat removal capability of these systems. Modify your test descriptions to include measurement of air and cooling water tem:eratures and fic'..s end the extrarolations that are nc: Essa j to.e y ths the ventilation syster.s can remove the postulated ;:s:-acciden: heat lcads.

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