ML19289G316
| ML19289G316 | |
| Person / Time | |
|---|---|
| Site: | Crane, Midland  |
| Issue date: | 03/09/1978 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19289G307 | List: |
| References | |
| NUDOCS 7908220466 | |
| Download: ML19289G316 (4) | |
Text
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211-15 211.0 REACTOR SYSTEMS 3 RANCH 211.85 It is noted that the pressurizer heaters and pressurizer safety (3.5.1.1) valves are not included in Tacles 3.5-1 or 3.5-2 nor are they discussed in Section 3.5.1.1.1.
If there is justificatien for not considering them as potential missiles, this shculd be addressed in Section 3.5.1.1.1.
If no justification exists, they should be included in Table 3.5-1 or 3.5-2.
221.86
. (3.5.1.1)'.
Verify that the following testing as required by Regulatory Guide 1.58 is being accomplished:
(1). icd centrol system alarms are verified to operate as required.
(2) The automatic reactor pcwer ecntrol system is verified to cpera:e as required.
(3) At least bio scram timings.? each red will be cerformed at extremes of temperature and flew.
2'11.37 Provide the ra:io of pressuri:ar and steam gene.rator safety (5.2.2.2) valve volumetric ficw rate to the peak surge r::e as Obtained fr:m the safety valve sizing analysis.
Since the pressurizer safety vaives nay be required to discharge liquid as weil as steam. provide this ratio for bc-h licuid and steam fl ws.
Shcw that this lat:er cacacf ty is ade uate for -hose ransients requiring liquid relief.
2'1.33
?rovice er referer.ce a discussion Of -he analytical basis for
'5.2.2.')
the st2an generat:r scfe:y valve set;;fnts, tolerance, and ca:acity.
2 '. '. 3 9 Verify tha-the sa'aty related ;u.aps, valves, and associa ed (5.-)
centrols are 1:ca ad above the ny;;;he-' cal water level esulting frca a LOCA.
Provide :he.credic ed 'l ed level calcula-ion wi n all assur:tions ider.-if f ec and jus-i'ied 'Or the. crst break locaticn (just'.fy the :reak selectac).
Submit laycut diagrams shcwing all systans bel w this s'evation.
Add a fac Or :: :he
~
' decc level calculati:n := ace:unt f:r uncertainties and fas:ify -his fac:cr.
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211-15 211.92 It appears : hat in the ECC code (suction fr:m 5'iST) the hPI (5.3.2.2) suction is not provided with ova. pressure protection.
Discuss the need for such protection in the suction pioing. Also, Table 9.3-14 shculd be expanded to include data on sizing criteria.
Include possible backpressure effects. Table 9.3-14 indicates 100 purcent accumulation. This erece shculd be corrected and the selected value should be justified.
211.93 Fer Table 3.2-1, it is noted that the "SW57 recir:ulation pump" (5.3) is not Seismic Category I.
Cescribe the function of this ECCS support component and justify its design.
211.94 Previde the basis for the use of less c nservstive oderator
(.5.0) coefficients in seme of the analyses (e.g., steam line break, loss of normal Figure 15.0 4, feedwater ficw, and feedwater line break).
which is referen:ed #cr these events, d:es not shew what specific. value is used in the an11vsis and also appears to be a factor of 10 tco low (10-! vice 10-").
_DDj(( U1b@db 2043 085 6
ENCLOSURE 2 Appendix laA d:es not include any test for the steam system 4) safety valves. Verify that the required test will be performed.
(ASS)
Standard Review Plan 6.3 acceptance criteria requires that 5.3)
ECCS be designed to perfora its function considering simultaneous LOCA and seismic loadings. Midland FSAR See:fon 5.3.1.4 states lead conditiens censidered were tnose conditions which might exist folicwing either a seismic or loss of coolant accident.
Further evaluation er justification should be performed.
(ME3) 3.
llRC staff to verify that Midland's position n Regulatcry (3.5.1.2)
Guide 1.14 as stated in Appendix 2A is acceptable (?tRC to CPC0 dated September 24,1976). ?fote that :nly one flywheel is being spin tested and that RC pump motors are no Seismic Category I.
(ME3) 2 flRC staff to verify that Midland's ?csition on Regulatcry (5.3)
Guide 1.32 as stated in Table 5.2-23 is ac:ectable.
lete that eniy one sump is provided.
(CSB) 5.
What precautions are taken to preclude c erat:r err:r when (2.5) reds are shifted from one gr:up to another grcup?
(C?5) 5.
Discuss the :ctential for a single failure resulting in a loss
$15.2.3) of A.rd to the unaffected steam genera:Or.
In : articular, c:nsider the inadvertent closure of valve IF73375A or 5 (L' nit 1) er 2FV3975A or 5 (Unit 2).
(AS3)
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The reac:ce building sum: 1 9es d: n:
se: ::ntain en:
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isolatien recuiremen:s (SRP 5.2.2 Ac:eo ance Oeiteria 25 an: d.
(C33)
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2043 086 6
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