ML17297B462

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Forwards Comments &/Or Inaccuracies Found in Nov 1981 SER, NUREG-0857
ML17297B462
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 04/16/1982
From: Van Brunt E
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To: Tedesco R
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0857, RTR-NUREG-857 ANPP-20721-WFQ, NUDOCS 8204210444
Download: ML17297B462 (10)


Text

SUBJECT:

For wards comments K/or inaccuracies found in Nov 1981 'SERg NUREG~0857

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ACCESSION NBR:8200210LIOQ DOC ~ DATE; 82/g0/16 NOTARI'ZED: YES FACIL:STN 50,528 Palo Ver de Nuclear Stationg Unit 1g Ar)zona Publi STN 50 529 Palo Verde Nuclear Stationg UniIt 2g Ar izona Publi STN 50 530 Palo Verde Nuclear Stationg Uni~t 3g Arizona 'Publi AUTH ~ NAME, AUTHOR AFFILIATION.

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PHOENIX, ARIZONA 65036 April 16, 1982 ANPP-20721-WFg/KNG Mr. R. L. Tedesco

'Assistant Director for Licensing Division of Licensing Office of the Nuclear Reactor Regulation Mashington, DC 20555

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Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Units 1, 2

6 3

Docket Nos. 50-528/529-530 Pile:

82-056-026/82-005-419.

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Reference:

NUREG-0857 dated

November, 1981, "Safety Evaluation Report Related to the Operation of Palo Verde Nuclear Generating Station, Units 1, 2 6 3

Dear Mr. Tedesco:

Please find attached a list of comments and/or inaccuracies found in the referenced document.

If you have any questions, please contact me.

EEVBJr/KMG/sb Attachment Very truly yours Q 'U E. E. Van Brunt, Jr.

APS Vice President, Nuclear Projects ANPP Project Director cc:

P. L. Hourihan A. C. Gehr R. L. Greenfield E. Licitra II 82042l0444 820416 PDR,ADOCK 05000528 PDR

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Attachment to ANPP-~721-WFQ/KWG April 16, 1982 Page Two the AFW system, will not occur.

For a description of the APS start-up testing commitment to be performed, refer to PVNGS FSAR Section

10A, question 10A.24.

13.

Page 10-19 (10.4.9.2.g)

Steam generator level is not controlled auto-matically by level signals to the AFWS control valves.

Rather, the system cycles on level switch signals.

See also CESSAR FSAR, Section 7.3.1.1.10.7.

14.

Pages ll-l (11.1),

11-2 (11.2.1),

Table 11.1, 11-9 (11.2.1.2),

11-10 (11.2.1.3) and 15-8 (15.4.9) refer to "shim bleed" which is not defined in the FSAR.

A definition should be provided by NRC in the SER.

15.

Page 12-2 (12.1.1)

The statement "The Radiation Protection Supervisor and the Health Physics personnel periodically review, update, and modify all plant design features, as well as all operating and maintenance

features, as appropriate, using exposure data and exper-ience gained from operating nuclear power plants," is overly broad and does not accurately reflect the responsibilities as outlined in the PVNGS FSAR, Section 12.5.1.

16.

Page 12-4 (12.1.5) In paragraph 2, "foreman" should be "personnel" per FSAR, Figure 13.1-6.

17.

Page 12-11 (12.5.4)

PVNGS has not committed to all plant personnel being badged, rather only those entering the restricted area.

Likewise, the bioassay program

~ma use the whole body counter or alternative methods.

For more information, see PVNGS FSAR, Section 12.5.3.6.

18.

Page 13-6 (13.1.1.2)

Paragraph 3, "Incumbent" is misspelled.

19.

Page 13-7 (13.1.1.2)

Paragraph 7, "Plant Manager" should be "Manager of Nuclear Operations."

(Refer to FSAR, Figure 13.1-6).

20.

Page 13-9 (13.1.1.2)

Paragraph 5 "The Chemical and Environmental Services Section" should be "Technical Services Section."

Refer to FSAR, Figure 13.1-6.

21.

Page 13-19 (13.2.2) "Training Director" should be "Training Manager" (in two places).

Refer to FSAR, Figure 13. 1-6.

22.

Page 13-22 (13.4.3.a) First sentence should have "ISEG" in place of "Safety Audit Committee."

Our response in FSAR question 13A.26 (page 13A-19) will be revised in a future amendment.

23.

Page 20-10 (Table 20.2) "South Carolina" should be "Southern California."

0

Attachment to ANPP-~21-WFQ/KWG

-; April 16-,-1982 Page One Comments on SER Related to the Operation of PVNGS NUREG-0857 dated

November, 1981 Page 6-1 (6.1.1)

Second paragraph reads in part, "(concentration 1720 ppm boron)."

The paragraph should read "(Concentration 4400 ppm maximum)" from FSAR 6. l.l.2 (page 6. 1-7).

2.

Page 6-10 (6.2.2)

Second paragraph implies that the operator must close the RWT isolation valve to complete the transition from safety injection mode to recirculation mode.

However, closure of the RWT isolation valves is not mandatory as discussed in FSAR Section 6A, Question 6A.42.

3.

Page 6-17 (6.2.4)

Second paragraph references a valve numbered CH-HV525, the correct number is CH-HV524.

Refer to FSAR Table 6.2.4-1 Sheet 6 of 8.

4.

Page 6-25 (6.3.3) APS'emonstration of power actuation and flow delivery will occur during preoperational (rather than pre-service) testing.

Refer to FSAR Chapter 14 for d'efinition.

5.

Page 8-20 (8.4.5)

Second paragraph, the correct valve numbers are JSIAUV634, JSIAUV644, JSIBUV614, and JSIBAUV624 as discussed in FSAR Appendix 8A, Question 8A.13 (page 8A-19).

6.

Page 9-4 (9.1.2) Part II.(second sentence)

states, "The pool contains...

approximately 2000 ppm of boric acid."

Please note that the 2000 ppm was an assumption used in evaluating criticality safety for a dropped bundle accident.

Actual concentration will be 4000-4400 ppm.

Refer to FSAR, Section 9.1.2.3.1 and FSAR Table 9.1-1.

7.

Page 9-6 (9.1.3)

The description given in the third paragraph is inaccurate.

For better information see PVNGS FSAR, Section 9A.34.

8.

Page 10-2 (10 ~ 2.1) In paragraph 4, point 5 should read "(5) Prolonged Loss Generator Stator Coolant."

Refer to FSAR Section 10.2.2.4, page 10.2-9A.

9.

Page 10-10 (10.4.4) Paragraph 4 describing the testing of the turbine bypass system does not agree with PVNGS FSAR Section 10.4.4.3 which describes the testing to be performed.

10.

Page 10-12 (10.4.6)

Second paragraph implies that the CDS serves only during start-up and periods of condenser

leakage, however it may be used continuously also.

Refer to FSAR Section 10.4.6.

Page 10-16 (10.4.9.1.d)

"Condensate storage pool" should be "Condensate storage tank."

12.

Page 10-18 (10.4.9.2.c)

APS has not committed to a start-up test using standard operating procedures to verify unacceptable water hammer in L

Pl STATE OF ARIZONA

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COUNTY OF MARICOPA)

I; Edwin E. Van Brunt, Jr., represent'hat I am Vice President Nuclear Projects of Arizona Public Service Company, that the foregoing document has been signed by me on behalf of Arizona Public'Service Company with full authority so to do, that I have read such document and know its contents, and that to the best of my knowledge and belief, the statements made therein are true.

Edwin E. Van Brunt, Jr.

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<Sworn to before me this' day of My Commission expires:

My 'Commission Exnires Oeo. 22. 1985 N]L

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Notary Public 198+

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