ML20244B681
| ML20244B681 | |
| Person / Time | |
|---|---|
| Issue date: | 10/10/1985 |
| From: | Gore A, Hauber R NRC OFFICE OF INTERNATIONAL PROGRAMS (OIP) |
| To: | Aleta C PHILIPPINES |
| Shared Package | |
| ML20244B550 | List: |
| References | |
| FOIA-89-99 NUDOCS 8904190331 | |
| Download: ML20244B681 (33) | |
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I U.S. NUCLEAR-REGULATORY COMMISSION 0FFICE OF INTERNATIONAL PROGRAMS PRIORITY UNCLASSIFIED l
-WASHINGTON, D. C. 20555 TLX: 710-824-0412 OCTOBER 10. 1985 xx A. GORE /R. D. HAUBER, IP 49-27131 tcc:
RHauber DCChaney ri kman Phil file MR. C. R. ALETA PHILIPPINE ATOMIC ENERGY COMMISSION METRO MANILA. THE PHILIPPINES TLX:
66804 PAEC PN THE FOLLOWING IS IN RESPONSE TO YOUR TELEX OF 10/7/85.
l AA) AT PRESENT. THE NRC DOES NOT REQUIRE PRE-0PERATIONAL TESTS PER-FORMED OVER A YEAR BEFORE ISSUANCE OF AN OL BE REPEATED UNLESS A SYSTEM HAS BEEN MODIFIED FOLLOWING PERFORMANCE OF A PRE-0PERATIONAL TEST ON THAT SYSTEM.
IF A SYSTEM WAS MODIFIED FOLLOWING PERFORMANCE OFAPRE-OPERATIONALTEST.THENRCWOULDREQUIRE(DEPENDINGUPONTHE' EXTENT OF THE MODIFICATION) THAT THE PRE-0PERATIONAL TEST BE REPEATED EITHER COMPLETELY OR AT LEAST ON THE AFFECTED PORTIONS OF
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THE SYSTEM. ALTHOUGH THE NRC DID NOT REQUIRE'!T TO DO S0 THE DIAELO CANYON LICENSEE DID REPEAT A FEW OF THE PREVIOUSLY PERFORMED PRE-OPERATIONAL TESTS ON SYSTEMS NOT MODIFIED BUT TESTED OVER A YEAR BEFORE.
l BB) TO ASSURE THE OPERABILITY OF SAFETY SYSTEMS FOLLOWING LONG DELAYS OF OPERATION, THE NRC REQUIRES LICENSEES TO PERFORM ALL THE l
APPLICABLE SURVEILLANCE REQUIREMENTS REQUIRED BY THE PLANT'S TECH-NICAL SPECIFICATIONS BEFORE A PLANT STARTUP FOLLOWING A LONG
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.8 TELEX MR. C. R. ALETA 2
TELEX: 66804 PAEC PN OUTAGE OR DELAY IN OPERATION. THESE REQUIREMENTS ARE SPECIFIED IN THE NRC STANDARD TECHNICAL SPECIFICATIONS (REF. SPEC. 4.0.4 0F THE W.,-STS.
I NUREG-0452ANDPNPP-1).
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CC) THE NRC HAS NOT IMPOSED ANY AD0!TIONAL GENERIC REQUIREMENTS AS A RESULT 1
0F THE JUNE 9,1985 DAVIS-BESSE INCIDENT. PLANT-SPECIFIC REQUIREMENTS FOR DAVIS-BESSE ARE NOTED IN NUREG-1154 AND IN A 10 CFR PART 50.54 (F) LETTER 4
1 SENT TO THE DAVIS-BESSE LICENSEE. THESE TWO ITEMS ARE BEING SENT TO YOU UNDER SEPARATE COVER.
REGARDS ADN HAUBER, NRC 1
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s si Coments on PNPP-1 Technical Specifications 1.
Suggested that consideration be given to revising Definition 1.25 (Reportable Occurrence) to be consistent with the changes which have been made by the issuance of 10 CFR 50.72 and 10 CFR 50.73.
These recomended changes were noted in Generic Letter 83-43, 2.
Recomended that Definition 1.27 (Shutdown Margin) be revised to required that the highest reactivity worth control rod cluster assembly q
always be considered fully withdrawn and unavailable for insertion. This allowance is necessary to account for an uncontrolled control rod cluster l
assembly' withdrawal.
- 3.,Su'ggested that all figures be printed on graph paper so that the limits can be accurately detemined.- Also note regions of unacceptable and acceptable operation.
4.
Recommended that the instrumentation tables be reviewed to. verify that the specified setpoints are consistent with the values, used in the safety analyses (Chapters 7 and 15 of FSAR) and that values be provided for all Functional Units. Also provided surveillance frequencies for all Functional Units.
l S.
Suggested that the Action Statements for Specs 3.1.1.1 and 3,1,1/2 be modified to make acceptable equivalent boration rates.
u 6.
Recomended that the Safety Injection Pumps be verified capable of injecting water from the RWST if they are to be considered an l
acceptable boration path in 3.1.2.2.
7.
Recommended that appropriate Surveillance Requirements be added to I
4.1.2.3 and 4.1.2.4 for the Safety Injection Pumps.
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Suggested that the minimum temperature requirements for the RWST be 8.
3.1.2.5, 3.1.2.6, and 4.1.2.5 since there is no danger deleted from of freezing at PNPP-1.
Recommended that the SfUrD0hN MARGIN be promptly detemined upon 9.
Also noted detection of a stuck control rod (Action a of 3.1.3.1).
that Action 3.b) could be deleted if other recommended changes associated with SHUTD0hN MARGIN are made (suggested those specs be!
made same as STS in hUREG-0452, Rev. 4).
- 10. It was noted that Functional Unit 8 (Loss of Power) of Tab referenced Action 19; however, the Table Notation for Table 3.3-3 Therefore, it is recommended an appro-does not include Action 19.
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.-i priate Action 19 be added to Table Notation.
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- 11. The Table Notation for Table 3.3-4 includes notation (6)
It was suggested not appear referenced anywhere on Table 3.3-4.
that reference to notation (6) be approximately included on Table 3.3-4 or that notation (6) be de,leted from the Table Notation.
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- 12. Table 3.3-6 includes several area radiation monitors which may not b It was suggested recuired to be included in the PNPP-1 Tech. Specs.
that the only radiation monitoring instruments required to be include (1) initiate EFS actions. (2) are used in Table 3.3 6 are those that to monitor RCS leakage, (3) are used to monitor for criticality in fuel storage areas, (4) are post accident monitors, and (5) are used for efflent monitoring.
- 13. It was suggested that Action 30 of Table 3.3-0 be revised to permit alternate means of monitorinc if the applicable instruments become inoperable. This change was nade in a Generic Letter on NURE The suggested change would pemit alternative means implementation.
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for monitoring while continuing plant operation (rather than requiring reactorshutdown).
- 14. It was recomended that Tables 3.2-9 and 4.3-6 be revised to include all the instruments needed to shutdown the reactor from the remote panel. Tables 3.3-10 and 4.3-7 should also be modified to list the PNPP-1 instruments.
15.
It was suggested that consideration be given to revising that entries in Table 3.3-11 (for minimum number of OPERABLE fire detection i
instruments) to require a specific number (the minimum required j
number) of fire detection instruments rather than "ALL."
16.
It was noted to PAEC that the W recomended frequency for perfoming SR 4.3.4.2.a has recently been changed from once per 7 days to once per 31 days. Recomended that consideration be given to making same change in PNPP-1 tech specs.
17 Recommended that PAEC request verification from the applicant (to be checked with W)-that 3.4.1.2.b which only requires one Reactor Coolant loop to be in operation in MODE 3 is still a valid assumption and requirement. This comment is in light of W recent notification I
to the USNRC that for the 3 and 4 loop plants at least 2 RC loops j
must be in operation to prevent DNB during a MODE 3 control rod withdrawal transient.
18.
Suggested that 3.4.6.1 be classified to require 3 RCS leakage detection j
systems be OPERABLE and that the Action Statement pemit operation to continue for up to 30 with only 2 systems OPERABLE SR 4.4.6.1.a should also be c'lassified accordingly.
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- 19. Since the charging pumps are assumed for use in the steam generator tube rupture accident, a limit of ~ 50% of the capacity of one i
charging pump should be included in 3.4.6.2 as a limit on i
CONTROLLED LEAKAGE. Also, an appropriate surveillance requirement for this leakage limit should be added to 4.4.6.2
- 20. Recomended that 3.5.5.a include a maximum limit on Rh3T water i
volume. A maximum limit is necessary for.pH control in the contain-ment sump during post accident conditions.
i 21.
Recomended that 3.6.1.2.a be deleted 'since a reduced pressure l
Type A containment leak rate test has not been performed and therefore 1
Lt cannot be properly specified in accordance with the provisions-
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of 10 CFR Part 50, Appendix J.
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- 22. Recomended that LCO 3.6.1.7 and SR 4.6.1.7 be added to the PNPP-1 Tech Specs to assure that the structural integrity of. the contain-ment is maintained.
23.
Suggested that PAEC have the applicant verify that the plant can be operated in accordance with 3.6.6 which prohibits use of the con-tainment purge system.
It is unlikely that the plant can be operated without being pemitted to use the purge system at all. Noma 11y',
plants are allowed to use the purge system for at least up to 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> l
per year (v1t of year).
24 Recommended that 4.6.2.2.d be modified to periodically (once per 5 years) demonstrate flow (either water or NaOH) thru the entire l
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NaOH flow path.
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- 25. Recommended the 4.6.8.1 and all other SR for charcoal and HEPA filter systems be modified per Generic Letter 83-13.
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- 26. Suggested that 3.7.9 be modified per Generic Letter 84-13. This-modification would delete Tables 3.7-4A and 3.7 48 and would then i
permit changes to the list of snubbers after an appropriate evalu-
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ation (per 10 CFR 50.59) by the licensee. This-will reduce the number of required license and amendments.
- 27. Recomended that 4.8.1.1.2.a.4 and 4.8.1.1.2.a.5 be modified in accordance with Generic Letter 84-15 which' reduces the number. of cold, fast starts required on the emergency diesel generators to only one per 6 months. This action is expected to improve overall diesel genera' tor reliability by reducing unnecessary stress and wear on the diesels.
- 28. Recommended that the reason for deleting the material in 4.8.2.3.b be detemined and reevaluated. (Deleted per FSAR Amendment No. 4). It appears that the noted material should not have been deleted.
29.
Recommended that PAEC verify that the various trip setpoints and other values specified in the PNPP-1 proposed Tech Specs be reviewed 1
against the safety analysis assumptions specified in the FSAR or 1
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other supporting documentation. It was noted that the PNPP-1 fetR-Sn u m i t, e w h <c.u ;s 4.J w:S n a ss a me w.d 4.* FNff-I A M
t Safety Analyses rather than with the W - STS (NUREG-0452, Rev. 4).
The Tech Specs must also include any requirements identified in the l
PAEC SER as being necessary to be included in the Tech Specs, 30.
Recommended that the need for 6.2.3 be reevaluated.
31.
Suggested that Table 6.2-1 be modified per Generic Letter 82-12 and 83-14 tc note that the overtime limits apply to more personnel than just the licensed operators.
32.
Recommended that the audit frequencies of 6.5.2.L.c and 6.5.2.8.f be changed to ence per 12 months. This change is necessary to make the I
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Tech Specs consistent with.the Regulations in'10 CFR and a recent-Generic Letter.
- 33. Recomended that 6.5.2.10.a - c be modified to specify to whom> these records are to be forwarded to.
- 34. Recomended that 6.6.1 and 6.9,1 be modified per Generic Letter 83-43 35.
Recomended that 6.7.1.e be added to state that critical operation of -
the unit shall be resumed (following a Safety Limit violation) until j
authorized by PAEC.
36.
Recomended that 6.8.4.d and e of the W-STS be added to PNPP-1 6.8.4 37.
Suggested that the detailed listing of various Special Reports in 6.9.2 be deleted since this listing is redundant to the requirements spelled out in the individual affected Tech Spec's.
- 38. Recomended that the applicant / licensee be requested and required to carefully review the proposed tech specs to verify that the proposed tech specs can be fully and completely implemented and that the proposed tech specs accurately reflect the as-built plant and FSAR.
If any differences are detected during this review, they should be resolved with and approved by PAEC.
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Summary and Recommendations
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1.
Although some minor modifications to the proposed technical specifica-tions are recomended, the PNPP-1 proposed technical specifications in
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general address the necessary topics to be included in the technical specifications for a typical plant of this type to be licensed in the United States in accordance with the current licensing requirements.
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The recommended modifications to the PNPP-1 proposed technical speci-j l
l fications are discussed in this report. The recommended changes are considered minor.
2.
PAEC must retain control of the PNPP-1 licensing process and should not be steam rolled by either the applicant or Westinghouse. PAEC j
should not be reluctant to impose any additional requirements in the PNPP-1 technical specifications which are indicated by its review of the PNPP-1 safety analysis to be necessary to assure the contiriued validity of the PNPP-1 safety analysis.
3.
PAEC should require _the applicant (NPC) to review the proposed tech-nical specifications to verify that the proposed technical specifications accurately reflect the as-built plant, that they are consistent with the safety analysis and that the requirements of the proposed technical specifications can be complied with and perfonned. Any inconsistencies noted during the applicant's review should be promptly brought to PAEC's attention for resolution prior to issuance of the Operating
- License, 4
PAEC and NPC should arrange meetings to resolve the recommended changes to the technical specifications.
5.
PAEC staff members should review their SER to ensure that all require ments(especially plant specific items) identified therein as requiring 1
1 technical specifications are actually included in the PNPP-1 technical
. _, x specifications to be' issued with the Operating License.
6.
It is recomended that a PAEC staff member be sent to the US NRC.
for some.on-the-job training with an Operating Reactor Project Manager to be trained in making license amendments since license amendments wi11'certainly be required periodically during plant operation. This training would be expected to require approximately 2-3 months.
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Comments on PfW-1 Technical Specifications 1.. Suggested that consideration be given to revising Definition 1.25 (Reportable Occurrence) to be consistent with the changes which have been made by the issuance of 10 CFR 50.72 and 10 CFR 50.73. These recommended changes were noted in Generic Letter 83-43, 2.
Recomended that Definition 1.27 (Shutdown Margin) be revised to require that the highest reactivity worth control rod cluster assembly I
i always be considered fully withdrawn and unavailable for insertion.
This allowance is necessary to account for an uncontrolled control rod cluster assembly withdrawal.
3.
R;co.; nded + hat tha def#nitiona in i.he Standei d Red iviagicai Effiueni; N NniOCl SpCC
$6di.50ild pc.t d) Tor VWK5 (iidRI.0-0472,ReVi5'un3)ve dd:d te the PNPP-1 Tech Sp;;; :nd that th RES bc dded te the-
'PNPP-1 Tech Sp;;%
Sugge:ted, th:t the phrace "and enmnly with the renoiramaatr of-9per
- cetier 6.'.1" bc added to the actinn Stat eert for speci<ication;-
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4.1.1. -
5.
Suggested that all Figures be printed on graph paper so that the limits can be accurately determined. Also note regions of unacceptable <a / accer 4 4 /e operation.
6.
Recomended that the instrumentation tables be reviewed to verify that the specified setpoints are consistent with the values, used in the safety analyses (Chapters 7 and 15 of FSAR) and that values be provided for all Functional Units. Also provide surveillance frequencies for all Functional Units.
t 7.
Suggested that the Action Statements for Specs 3.1.1.1 and 3.1.1.2 be modified to make acceptable equivalent boration rates.
4h Rocnnmanana tha+ (urveillan c Requirements be added to 4.1.1.1 and A.1.1.2 tG idqu ii 6 pFOGpt (Within 1 h0Ui ) vei IIIs6tiUR Of SIlUIDOWN
_EARCIF if ; centre' rad ie datermined te be inoperable.
9.
Recommended that the Safety Injection Pumps be verified capable of injecting water from the RWST if they are to be considered an acceptable boration path in 3.1.2.2.
- 10. Recommended that appropriate Surveillance Requirements be added to 4.1.2.3 and 4.1.2.4 for the Safety Injection Pumps.
- 11. Suggested that the minimum temperature requirements for the RWST be deleted from 3.1.2.5, 3.1.2.6 and 4.1.2.5 since there is no danger of freezing at PNPP-1.
- 12. Recommended that the SHUTDOWN MARGIN be promptly determined upon detection of a stuck control rod (Action a of 3.1.3.1).
Also noted that Action 3.b) could be deleted if other recommended changes associated with SHUTDOWN MARGIN are made (suggested those specs be 4
made same as STS in NUREG-0452, Rev. 4).
-13.
00 cmrended that 4.2.3.3 Gf 'iSTSbc:dd:dtoPNPP1TcchSpecs-
-(ma k e na r+ nr a 2.31 shnu1d verif,R;S i;v.cate acre ;ften th3m
> ^nl y nace per 31 EFPO.
14.
It was noted that Functional Unit 8 (Loss of Power) of Table 3.3-3 referenced Action 19; however, the Table Notation for Table 3.3-3 not doesA nclude Action 19. Therefore, it is recommended an appropriate i
l Action 19 be added to the Table Notation.
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- 15. The Table Notation for Table 3.3-4 includes notation (6) which does not appear referenced anywhere on Table 3.3-4.
It was suggested that reference to notation (6) be approximately included on Table 3.3-4 or that notation (6) be deleted from the Table Notation.
- 16. Table.3.3-6 includes several area radiation monitors which may not.be required to be included in the PNPP-1 Tech Specs.
It was suggested that the only radiation monitoring instruments required to be included in Table 3.3-6 are those that (1) initiate EFS actions, (2) are "S*l to monitor RCS leakage, (3) are used monitor for criticality in fuel storage areas, (4) are post accident monitors, and (5) are used for effluent monitoring.
17.
It was suggested that Action 30 of Table 3.3-6 be revised to pennit alternate means of monitoring if the applicable instruments become inoperabl e.
This change was made in a Generic Letter on NUREG-0737 I
implementation. The sugge'sted change would pennit alternative means for monitoring while continuing plant operation (rather than requiring reactorshutdown).
-10.
It. ins suggcste that the l htM -c :gre,A ianves v.' 0;1: be, evieweu
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-te '/;rifi d Uici, uc,c;;tn::: " T:bl: 3.3 h-12 't J efude a tt /A <
19.
It was recommended that Table %4.3-6 be revised to.p; cen;i:t:nt "ith e% s % ~ a Js ne e d e d do shuloG Me rea c h e f, e m -/A t r e d<
11 in:telicJ i.n FnFF A. fr.r /
T;bi; 3.3 9 aM te l ht th;d 4.3-7.rk::N":
in:tru= cat-m ise he w h rj pa n < l. Te i les f, ] -t e a n n ia cm.nent E :!:e :p-li able to T;bl:: ?.?-10 : M a ? 5
.#e futf-t
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- dr, 20.
It was suggested that consideration be given to revising that entries in Table 3.3-11 (for minimum number of OPERABLE fire detection instruments) to require a specific number (the minimum required number) of fire i
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detection instruments rather than "ALL."
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V 21.
It was noted to PAEC that the W recommended frequency for performing SR 4.3.4.2.a has recently been changed from once per 7 days to once per 31 days. Ree o. ~ h 'I 0 W " ' ' A " # * '
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- 22. Recommended that PAEC request verification from the applicant (to be I
checked with W) that 3.4.1.2.b which only requires one Reactor Coolant.
s h u a va t;.I a ss u ~ p H...< o J r #9 "l- < *A M i
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in operation in MODE 3 isA n light of W recent notification'ri'p #'
i loop to be to the USNRC that for the 3 and 4 loop plants at least 2 RC loops must be in operation to prevent Of6 during a MODE 3 control rod withdrawal transient.
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- 23. Suggested that 3.4.6.1 be clasified to require 3 RCS leakage detection systems be OPERABLE and that the Action Statement permit operation to continue for up to 30 with only 2 systems OPERABLE.
should also be clasified accordingly.
- 24. S%ened FACC dot,oi ua n: p4 'a mm << e ass- - a J Ae use i.,
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the che-a4 ng nomne are t:ker, credit fcr p,, a. k r lab <. r u e +< < < a c.' J r.,1 sS a limit of s 50% of the capacity of one 4#
-th: ::.fety ;&l p :3, charging pump should be included in 3.4.6.2 as a limit on CONTROLLED
<o e.' a ie s u v a e t it* ~ < e regu <ene.<f 4,<
piso, an < < r mma 4. 5 3 t;ner in 33fety 3n31y34 3,.se egnth 7 LEAKAGE. u m-~m.
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.h:2 le < 6. s s e
/,% 4 s/u s /d b < a JJ< J 4 4.4. C L
- in y ara reau4 red. This ::- ent 4e alen anniirahic to 3.5.2 and O.
that ; I cic,ence bond be i cludcA #cr the wate-vele=e 25.
"^cc - ^r.ded t
n in 3.5.i.1.6.
- 26. Recomnjended that 3.5.5.a. include a maximum limit on RWST water volume. A m,i,,,,,,,
/,% ; + o.s ase< <rre.] 4 < p H e c.d. i k L e c.< h t.. n e.. +
.r u ~ y, aw,,,
- 27. Recomended that 3.6.1.2.a.2 be deleted since a reduced pressure /"*> ' - a c< ' s,_ 4 e c., s, i..,.,,*
Type A containment leak rate test has not been performed and therefore Lt cannot be properly specified in accordance with the provisions of 10 CFR Part 50, Appendix J.
^ 1 :e raenmmend ed u m i Fa be Ch669cd I'vm J d A nr,i g, Aich i; the hio iwoent design pi c55drC, tC
.' psi 9
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~hich-1: the c:lculeied peak eccident gi cssu, e.
- 28. Recomended that LC0g 3.6.1.7 and 3.5.0.0-SRy 4.6.1.7 : 'd d.tS.3 be added to the PNPP-1 Tech Specs to assure that the structural integrity i
of the containment is maintained.
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- 29. Suggested that PAEC have the applicant verify that the plant can be 6
operated in accordance with 3.6.1.8 which prohibits use of the containment purge system.
It is unlikely that the plant can be operated without being permitted to use the purge system at all.
Nonnally, plants are allowed to use the purge systen for at least up to 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> per year (s 1% of year).
- 30. Recomended that 4.6.2.2.d be modified to periodically (once per 5 years) demonstrate flow (either water or Na0H) thru the entire NaOH flow path.
- 31. Recomended the 4.6.8.1 and all other SR for charcoal and HEPA l
filter systems be modified per Generic Letter 83-13.
- 32. Suggested that 3.7.9 be mcdified per Generic Letter 84-13. This I
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modification would delete Tables 3.7-4A and 3.7-4B and would then permit changes to the list of snubbers after an appropriate evaluation l
(per 10 CFR 50.59) by the licensee. This will reduce the number of required license and amendments.
- 33. Recommended that 4.8.1.1.2.a.4 and 4.8.1.1.2.a.5 be modified in accordance with Generic Letter 84-15 which reduces the number of cold, f
l fast starts required on the emergency diesel generators to only one j
per 6 months. This action is expected to improve overall diesel generator reliability by reducing unnecessary stress and wear on the dies el s.
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b 34 Recomended that the reason for deleting the material in 4.8.2.3.5 be determined and reevaluated. (Deleted per FSAR Amendment No. 4).
It appears that the noted material should not have been deleted.
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- 35. Recomended that PAEC verify that the various trip setpoints and other values specified in the PNPP-1. proposed Tech Specs be reviewed against the safety analysis assumptions specified in the FSAR or other supporting documentation.
It was noted that the PNPP-1 Tech j
Specs must be made consistent with the assumptions of the PNPP-1 FSAR safety analyses rather than with the W-STS (NUREG-0452, Rev. 4). The Tech Specs must also include any requirements identified in the PAEC SER as being necessary to be included in the Tech Specs.
.ti. e na<J Sa Recommended that 6.2.3 ber-f etad W W ittM Ter MEC cv 6.
36.
3 n e tu.1< 2.
- 37. Suggested that Table 6.2-1 be modified per Generic Letter 82-12 and 83-14 to note that the overtime limits apply to more personnel than just the licensed operators.
- 38. Recomended that the audit frequencies of 6.5.2.8.e and 6.5.2.8.f be changed to once per 12 months. This change is necessary to make the Tech Specs consistent with the Regulations in 10 CFR and a recent Generic Letter, g 4 /. a )
- 39. Recomended that.6.5.2.10.a - c be =defced to specify to whom these records are to be fowarded to.
- 40. Recommended that 6.6.1 and 6.G.1 be modified per Generic Letter 83-43.
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- 41. Recomended that 6.f.1.e be added to state that critical operation of the unit shall not be resumed (following a Safety Limit violation) until authorized by PAEC.
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- 42. Recomended that 6.8.4.d and e of the W-STS be added to PNPP-16.8.4
- 43. Suggested that the detailed listing of various Special Reports in 6.9.2 be deleted since this listing is redundant to the requirements spelled out in the individual affected' Tech Specs.
i 44 Recommended that the applicant / licensee be requested and required to carefully review the proposed tech specs to. verify that the proposed tech specs can be fully and completely implemented and that the proposed--
tech specs accurately reflect the as-built plant and FSAR. -If any
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differences are detected during this review, they should be resolved with and approved ' by PAEC.
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- 26. Suggested that 3.7.9 be modified per Generic Letter 84-13. This modi-fication would delete Tables 3.7-4A and 3.7-4B and would then pemit changes to the list of snubbers after an appropriate evaluation (per 10 CFR 50.59) by the licensee. This will reduce the number of required license and amendments,
- 27. Recomended that 4.8.1.1.2.a 4 and 4.8.1.1.2.a.5 be modified in accor-dance with Generic Letter 84-15 which reducec the number of cold, fast starts required on the mergency diesel generators to only one per 6 months. This action is expected to improve overall diesel generator reliability by reducing unnecesary stress and wear on the diesels;
- 28. Recomended that PAEC verify that the various trip setpoints and other values specified in the PNPP-1 proposed Tech Specs be reviewed against i
the safety analysis assumptions specified in the FSAR or other supporting documentation.
It was noted that the PNPP-1 Tech Specs must be made consistent with the assumptions of the PNPP 1 FSAR safety analyses rather than with the W-STS (hUREG-0452, Rev. 4). The Tech Specs must also include any requirements identified in the PAEC SER as being necessary to be included in the Tech Specs,
- 29. Recomended that the need for 6,2,3 bereevaluatedi 1
- 30. Suggested that Table 6.2-1 be modified per Generic Letter 82,12 and 83-14 to note that the overtime limits apply to more personnel than j
justthelicensedoperators, Recomended that the audit frequencies of 6,5,2,8,e and 6,2,8,f be changed to once per 12 months. This change is necessary to make I
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